ML12290A087

Bellefonte Nuclear Plant, Units 1 and 2, Proposed Regulatory Framework for the Possible Completion of Construction Activities

ML12290A087
Person / Time
Site:	Bellefonte
Issue date:	10/10/2012
From:	Stinson K Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12290A087 (164)

Text

Tennessee Valley Authority, 2744 Bellefonte Road, OSB I A, Hollywood, Alabama 35752 October 10, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Bellefonte Nuclear Plant, Units 1 and 2 Construction Permit Nos. CPPR-122 and CPPR-123 NRC Docket Nos. 50-438 and 50-439

Subject:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - PROPOSED REGULATORY FRAMEWORK FOR THE POSSIBLE COMPLETION OF CONSTRUCTION ACTIVITIES

References:

1. Letter from TVA to NRC, "Bellefonte Nuclear Plant (BLN) Units 1 (CPPR-122) AND 2 (CPPR-123)- Transition to Deferred Status,"

dated August 10, 2009 [ML092230730].

2. Letter from TVA to NRC, "Bellefonte Nuclear Plant (BLN) Units 1 (CPPR-122) and 2 (CPPR-1 23)- Key Regulatory Assumptions for the Possible Completion of Construction Activities," dated April 9, 2010

[ML101050030].

3. Letter from NRC to TVA, "Bellefonte Nuclear Plant, Units 1 and 2 -

Regarding Key Assumptions for Reactivation," dated August 4, 2010

[ML101880337].

4. Letter from TVA to NRC, "Bellefonte Nuclear Plant Units 1 and 2 -

Proposed Regulatory Framework for the Possible Completion of Construction Activities," dated May 5, 2011 [MLI 1132A1 18].

5. Letter from TVA to NRC, "Updated Bellefonte Quality Verification Program," dated August 28, 2012 [ML12249A006].

In TVA's letter to the NRC requesting transition to deferred status dated August 10, 2009 (Reference 1), TVA communicated its intent to develop a detailed Regulatory Framework for Bellefonte (BLN) Units 1 & 2. The BLN Regulatory Framework establishes the proposed BLN licensing basis TVA intends to use for BLN to update the Final Safety Analysis Report (FSAR). TVA believes that providing the BLN 1 & 2 Regulatory Framework for NRC staff review is consistent with the licensing process used

U.S. Nuclear Regulatory Commission Page 2 October 10, 2012 to establish the Regulatory Framework for the restart of Browns Ferry Unit 1 and the initial licensing of Watts Bar Unit 2.

In TVA's letter to the NRC dated April 9, 2010 (Reference 2), TVA described the key assumptions for the possible completion of construction activities that would guide the development of the BLN 1 & 2 Regulatory Framework. The proposed BLN 1 & 2 Regulatory Framework was developed based on the key assumption that TVA would perform a case-by-case review of new regulations and guidance consistent with Section Ill.A.5 of the NRC Policy Statement on Deferred Plants, Generic Letter 87-15. As part of this review, TVA would continue to look for opportunities to improve plant systems and design. TVA also assumed that the NRC would apply licensing standards in the same manner as for a plant under construction, taking into account the dates of the Construction Permits (December 1974) and Operating License application (February 1978), as addressed under the Policy Statement on Deferred Plants. The NRC provided a response to TVA's key regulatory assumptions by letter dated August 4, 2010 (Reference 3). Therefore, TVA's key regulatory assumptions and subsequent NRC feedback form the basis for determining the applicable requirements for BLN.

TVA submitted the initial BLN 1 & 2 Regulatory Framework in a letter dated May 5, 2011 (Reference 4). Since that time, TVA has conducted extensive engineering design evaluations and plant walkdowns that refine and clarify its proposed licensing basis and positions. This letter supersedes TVA's May 5, 2011 letter in its entirety and provides the current approach TVA has taken to establish the proposed Regulatory Framework for the possible completion of BLN 1 & 2 for NRC staff review. Enclosure 1, "TVA's Proposed BLN Regulatory Framework," provides the tables described in this letter that collectively establish the proposed BLN Regulatory Framework.

The scope of TVA's review to establish the BLN Regulatory Framework included an evaluation of regulatory guidance found in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition" (SRP),

applicability of NRC Generic Letters and Bulletins, and applicability of NRC Unresolved Safety Issues (USIs). The development and submittal of the BLN Regulatory Framework is consistent with the provisions of the Policy Statement on Deferred Plants, Sections IIl.A.6.d and III.A.6.e.

TVA is adopting, when feasible, the acceptance criteria contained in the SRP up to the revisions in effect as of the date of this letter as the licensing basis for BLN 1 & 2. When full adoption of the acceptance criteria in the current SRP is not feasible, TVA has identified the deviation and provides an alternative with an acceptable method of compliance with the NRC rules, regulations, and regulatory guidance that underlie the corresponding SRP acceptance criteria.

U.S. Nuclear Regulatory Commission Page 3 October 10, 2012 TVA's comprehensive review of the current SRP consisted of the following major elements:

a. TVA performed a section by section review of requirements', regulatory guidance, and applicable industry codes and standards, as specified in Section II, "Acceptance Criteria," of each SRP section. For some SRP chapters, regulatory requirements and acceptance criteria are also contained in tables (e.g., Table 7-1). These requirements and acceptance criteria were also included and evaluated in the review. Regulatory guidance found in the "Review Procedures" section of the SRP was also considered in the review.

b. TVA identified key licensing issues and their current status. These issues may be unresolved due to factors such as regulatory history, length of the BLN 1 & 2 licensing process, unique B&W issues, or other industry or BLN 1 & 2 specific issues. The issues include those identified in the TVA position papers submitted in the early 1990's and evaluated by NRC during that time period. The issues are identified in the discussion regarding related SRP sections and the key requirements from these sections have been linked to the issues.

The results of TVA's evaluation of BLN 1 & 2 plans to conform with the SRP are documented in Table 1 of Enclosure 1, "BLN Conformance with the NRC Standard Review Plan."

Table 1 contains seven columns. Column 1 identifies the Final Safety Analysis Report (FSAR) section number and title, as provided in RG 1.70 (Rev. 3), "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)."

Discussion with NRC staff indicated that including this column would benefit the staff in their review.

Column 2 identifies the number and title of each SRP section. The SRP sections are cross-referenced with the appropriate FSAR section. The SRP section numbers and titles generally align with the format provided in RG 1.70, although there are some minor differences. For example, section 2.4.12 of RG 1.70 addresses "Dispersion, Dilution and Travel Times of Accidental Releases of Liquid Effluents in Surface Waters," whereas the corresponding section of the SRP is numbered 2.4.13 and is, titled "Accidental Releases of Radioactive Liquid Effluents in Ground and Surface Waters."

1 The requirements that must be met before a plant can be licensed are defined in NRC regulations.

The NRC staff has prepared a number of guidance documents, such as the Standard Review Plan and regulatory guides, that are acceptable to the NRC staff for meeting various requirements in the regulations. Except for a few regulatory guides that are specifically referenced in a regulation, these guidance documents are not requirements. Neither the SRP nor the Regulatory Guides reviewed in this analysis is a substitute for the NRC's regulations and compliance is not required.

U.S. Nuclear Regulatory Commission Page 4 October 10, 2012 Column 3 identifies the revision of the SRP acceptance criteria that formed the baseline for TVA's review. In each case, the revision identified is the current revision in effect as of the date of this letter.

Column 4 includes the list of the NRC regulations and guidance that TVA intends to use with regard to the Acceptance Criteria contained in the SRP. Any exceptions to the SRP Acceptance Criteria are explained in Column 7, "Additional Information." Column 4 also specifies the revisions (in the case of Regulatory Guides) and dates (in the case of industry standards) TVA intends to use for the completion of Bellefonte. Where the latest revision of a regulatory guide or industry standard is not used, a note is included in Column 7 to clarify TVA's licensing position.

Column 5 includes a summary of the key issues related to each SRP section as described above.

Column 6 includes a current status of each key issue as determined by review of docketed correspondence.

Column 7 includes additional information pertaining to the associated SRP section or key issues. In addition to exceptions taken to the SRP, it includes regulatory guidance that TVA intends to include in its licensing basis that is not referenced in the SRP. This guidance includes recently issued Regulatory Guides, TMI Items that are applicable to BLN but that are not referenced in the SRP, and other relevant regulatory guidance provided by the NRC.

TVA has also reviewed NRC generic letters and bulletins. Table 2, "Generic Communications - Applicability and Status for BLN Units 1 & 2," of Enclosure 1 provides a status of generic communications with respect to BLN 1 & 2. This table includes NRC generic communications, their applicability to BLN 1 & 2, status, and proposed actions.

As indicated in Table 2, many of the requirements and actions associated with the generic communications have been embodied in the later revisions of the SRP. When the generic communication is referenced directly in the SRP or the applicable guidance is incorporated into the SRP, the generic communication is not listed in Table 1 for brevity. In cases where TVA identified that the generic communication was relevant and not fully addressed in the SRP, the generic communication was added to Table 1 in Column 7. TVA also identified cases where the actions required by the generic communications will be superseded by the Refurbishment Program described in the Bellefonte Quality Verification Program (Reference 5). Items wherein TVA believes all actions required to address the generic communication will be completed as a logical part of its plant completion activities are identified as "Closed." TVA will maintain Table 2 to provide the NRC with an updated status of the generic communications. Generic letters or bulletins applicable to Bellefonte that are issued between the date of this letter and the submittal of the Construction Reactivation letter will be added to this list. Once the Construction Reactivation letter is submitted, future generic communications will be

U.S. Nuclear Regulatory Commission Page 5 October 10, 2012 responded to in accordance with the schedule of the individual generic communication and added to Table 2.

Similar to TVA's review of NRC generic communications, TVA also reviewed NRC Unresolved Safety Issues (USI's) for applicability and status at BLN 1 & 2. Table 3, "Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2," of provides the same type of information for each USI as is provided for generic communications in Table 2.

This submittal of the BLN 1 & 2 Regulatory Framework is based on information available as of the date of this letter. The potential for changes to this framework based on evolving regulatory issues and emergent information during design completion and project planning exists. Should TVA determine, based on further review or emerging issues, that a different approach or additional action is appropriate, TVA will submit such changes to the NRC for review. These changes will be provided in periodic updates to the BLN 1 & 2 Regulatory Framework tables as actions are completed. of this letter includes the tables referenced in this letter that collectively provide the proposed BLN Regulatory Framework. provides a list of TVA commitments made in this letter.

If you have any questions concerning this matter, please call Erin West (256) 574-8265.

Sincerely, K. David Stinson, Jr.

Vice President Bellefonte Nuclear Plant Enclosure(s):

1. TVA's Proposed BLN Regulatory Framework

2. List of TVA Commitments cc: See page 6

U.S. Nuclear Regulatory Commission Page 6 October 10, 2012 cc (w/Enclosures):

U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave. NE, Suite 1200 Atlanta, Georgia 30303-1257 TVA Letter dated October 10, 2012 TVA's Proposed BLN Regulatory Framework Table 1 - BLN Conformance with the NRC Standard Review Plan Table 2 - Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Table 3 - Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information Section Revision Criteria KAcceptance A lStatus RG 1.70 (FSAR) Section Chapter 1 - Introduction and General Description of Plant

1. Introduction and General None Description of Plant None 1.0 Introduction and 2011 10 CFR 50.33, .34 None NA This section is a general overview of the FSAR.

Interfaces 1.1 Introduction None 1.2 General Plant None Description 1.3 Comparison Tables None 1.3.1 Comparisons with None Similar Facility Designs 1.3.2 Comparison of Final None and Preliminary Information 1.4 Identification of Agents None and Contractors 1.5 Requirements for None Further Technical information 1.6 Material Incorporated None by Reference 1.7 Drawings and Other None Detailed Information 1.7.1 Electrical, None Instrumentation, and Control Drawings 1.7.2 Piping and None Instrumentation Diagrams Page 1 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRPRASRP Secteon Key IsKeesus Additional information G.7nSection Revision Acceptance Criteria ssue~s) Status 1.7.3 Other Detailed None Information 1.8 Conformance to NRC None Regulatory Guides 1.9 Standard Designs None 1.9.1 Interfaces None 1.9.2 Exceptions None Page 2 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Information Section Revision Acceptance Criteria suesAdditional RG 1.70 (FSAR) Section Chapter 2 - Site Characteristics

2. Site Characteristics 2.0 Site Characteristics NA None NA SRP Section 2.0 is not applicable to CP & OL applications and Site Parameters submitted under 10CFR50.

2.1 Geography and None None None NA Demography 2.1.1 Site Location and 2.1.1 10 CFR 50.34(a)(1) None NA Although the BLN site was initially approved in compliance Description 10CFR 100, Subpart B with the reactor site criteria in 10 CFR 100 Subpart A (100.10 & .11), providing the NRC assurance of BLN 2007 compliance with the reactor site criteria in 10 CFR 100 Subpart B (which includes 100.20, .21, .23 & Appendix A) is consistent with TVA's decision to comply with 10 CFR 50 App S (see sect. 3.7.1).

2.1.2 Exclusion Area 2.1.2 10 CFR 100, Subpart B None NA Authority and Control 2007 10 CFR 50.33, .34(a)(1) 2.1.3 Population 2.1.3 10 CFR 50.34(a)(1), None NA Distribution 2007 10 CFR 100, Subpart B RG 1.70 R3, 4.7 R2 Positions C.3

& 0.4 2.2 Nearby Industrial, None Transportation, and Military Facilities 2.2.1 Location and Routes 2.2.1 - 2.2.2 Identification 10 CFR 50.34(a)(1)(i) Potential Aircraft See Section 2.2.2 Descriptions of Potential Hazards in 2007 10 CFR 100, Subpart B Hazard 3.5.1.6.

Site Vicinity RGs 1.70 R3, 1.91 R1 2.2.3 Evaluation of 2.2.3 10 CFR 100, Subpart B Potential Aircraft See Section Potential Accidents 10 CFR 50.34(a)(1)(i) Hazard 3.5.1.6.

Page 3 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status 2.3 Meteorology None 2.3.1 Regional Climatology 2.3.1 10 CFR 50 App. A GDC 2, 4 None NA 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.76 R1 2.3.2 Local Meteorology 2.3.2 10 CFR 50 App. A GDC 2 None NA 2007 10 CFR 100, Subpart B RGs 1.23 R1, 1.70 R3 2.3.3 Onsite Meteorological 2.3.3 10 CFR 50 App. A GDC 19, App. I, None NA Measurements Program .47(b)(4,8,9), App. E Sect. IV.E.2 2007 10 CFR 100, Subpart B 10 CFR 20 Subpart D RG 1.23 R1 2.3.4 Short-Term Diffusion 2.3.4 Short-term 10 CFR 50 App. A GDC 19 None NA Estimates Atmospheric Dispersion 10 CFR 50.34(a)(1)(ii)(d)

Estimates for Accident 2007 10 CFR 100, Subpart B Releases RGs 1.23 R1, 1.70 R3, 1.78 R1, 1.145 R1, 1.194 RO 2.3.5 Long-Term Diffusion 2.3.5 Long-Term 10 CFR 50, .34a, App. I None NA Estimates Atmospheric Dispersion 10 CFR 20 Subpart D Estimates for Routine 2007 10 CFR 100, Subpart B Releases RGs 1.23 R1, 1.70 R3, 1.109 R1, 1.112 RI 2.3.6 BOP Interface None 2.4 Hydrologic Engineering None Page 4 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) A RG 1.70 (FSAR) Section Section RevAcceptance Criter Key Issue(s) Additional Information 2.4.1 Hydrologic 2.4.1 10 CFR 50 App. A GDC 2 None NA Description 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2,1.102 R1 2.4.2 Floods 2.4.2 10 CFR 50 App. A GDC 2 Updated Design Open BLN 3&4 PMF and seismic dam failure submittals have 10 CFR 100, Subpart B Basis Flood Level been sent to NRC and contain site-specific information RGs 1.27 R2 (For Comment), 1.29 applicable to BLN Units 1&2.

2007 R4, 1.59 R:2, 1.102 Ri

"-TVAwill provide the information required by the March 12, 2012 NRC Request for Information (RFI) regarding flooding reevaluations in accordance with the established timeframes.

2.4.3 Probable Maximum 2.4.3 10 CFR 50 App. A GDC 2 See 2.4.2. Open Flood (PMF) on Streams and Rivers 2007 10 CFR 100, Subpart B 10CR0,SuprB RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1.102 R1 2.4.4 Potential Dam 2.4.4 Potential Dam 10 CFR 50 App. A GDC 2, 44 See 2.4.2. Open Failures, Seismically Idcd2007 Failures 10CFR100, 10CR10SuprB Subpart B Induced 2 RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1.102 R1 2.4.5 Probable Maximum 2.4.5 10 CFR 50 App. A GDC 2,44 See 2.4.2. Open Surge and Seiche Flooding 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1.102 RI 2.4.6 Probable Maximum 2.4.6 Probable Maximum 10 CFR 50 App. A GDC 2 None NA Tsunami Flooding Tsunami Hazards 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1,102 R1 Page 5 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (,SAR Section Section( Revision Acceptance Criteria Status 2.4.7 Ice Effects 2.4.7 10 CFR 100, Subpart B None NA 2007 10 CFR 50 App. A GDC 2 RGs 1.27 R2, (For Comment) 1.29 R4, 1.59 R2, 1.102 R1 2.4.8 Cooling Water Canals 2.4.8 10 CFR 50 App. A GDC 1,2,44 None NA and Reservoirs 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1.102 R1, 1.125 R2 2.4.9 Channel Diversions 2.4.9 10 CFR 50 App. A GDC 1,2,44 None NA 2007 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.29 R4, 1.59 R2, 1.102 R1 2.4.10 Flooding Protection 2.4.10 10 CFR 50 App. A GDC 2,44 None NA Requirements 2007 10 CFR 100, Subpart B RGs 1.29 R4, 1.59 R2, 1.102 R1 2.4.11 Low Water 2.4.11 10 CFR 50 App. A GDC 2,44 None NA Considerations 2007 10 CFR 100, Subpart B RG 1.27 R2 (For Comment), 1.29 R4 2.4.12 Dispersion, Dilution, 2.4.13 Accidental 10 CFR 100, Subpart B None NA and Travel Times of Releases of Radioactive 10 CFR 50 App. A GDC 2 Accidental Releases of Liquid Effluents in Ground 2007 BTP 11-6 Liquid Effluents in Surface and Surface Waters RG 1.113 R1 Waters 2.4.13 Groundwater 2.4.12 Groundwater 10 CFR 50.55, 50.55a, None NA 10 10 CFR CFR 50 100,App. A, GDC Subpart B 2,4,5,44 RG 1.27 R2 (For Comment)

Page 6 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section [ Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status Sp4.14 Technical 2.4.14 10 CFR 50.36 None NA Specification and 10 CFR 50 App. A GDC 2,44 Emergency Operation 2007 10 CFR 100, Subpart B Requirements RGs 1.29 R4, 1.59 R2, 1.102 R1 2.5 Geology, Seismology, None and Geotechnical Engineering 2.5.1 Basic Geologic and 2.5.1 1.0 CFR 50 App. A GDC 2 Seismic Information 10 CFR 100, Subpart B RGs 1.132 R2, 1.138 R2, 1.198 RO, 1.208 RO, 4.7 R2 2.5.2 Vibratory Ground 2.5.2 10 CFR 50 App. A, GDC 2 Design basis Resolution of this NRC SER dated October 4, 1991 in response to TVA Motion 10 CFR 100, Subpart B earthquake using issue will address position paper accepted ground response spectra RGs 1.60 R1, 1.132 R2, 1.208 RO, updated GMRS TVA position anchored to an acceleration of 0.1 8g 4.7 R2 site specific paper on ground spectra (based motion dated Spectra satisfy RG 1.208 requirements.

on 1989 EPRI- 2/14/1991 (TAC 2007 SOG), with a No. 79275; minimum 0.1g M1 11151364) earthquake, to requirements of Appendix S, including updated soil investigation.

2.5.3 Surface Faulting 2.5.3 10 CFR 50 App. A, GDC 2 None NA 10 CFR 100, Subpart B RGs 1.132 R2, 1.198 R0, 1.208 RO, 4.7 R2 Page 7 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status 2.5.4 Stability of 2.5.4. 10 CFR 50.55a, App. A GDC None NA Subsurface Materials and 1,2,44, App, B, App. S Foundations 2010 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.28 R4, 1.132 R2, 1.138 R2, 1.198 RO 2.5.5 Stability of Slopes 2.5.5 10 CFR 50.55a, App. A, GDC None NA 1,2,44, App. B, App. S 2010 10 CFR 100, Subpart B RGs 1.27 R2 (For Comment), 1.28 R4, 1.132 R2, 1.138 R2, 1.198 RO 2.5.6 Embankments and None Dams Page 8 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 3 - Design of Structures, Components, Equipment, and Systems

3. Design of Structures, None Components, Equipment, and Systems 3.1 Conformance with NRC None General Design Criteria 3.2 Classification of None Structures, Components, and Systems 3.2.1 Seismic Classification 3.2.1 2007 10 CFR 50, App. A, GDCs 1,2,61, None NA For existing (legacy) equipment TVA will use RG 1.151 RO.

App B and App. S For newly procured/major modified equipment, TVA will 10 CFR 100, Subpart B use RG 1.151 RI.

RGs 1.29 R4, 1.143 R2, 1.151, 1.189 R2 3.2.2 System Quality Group 3.2.2 2007 10 CFR 50, App. A, GDC 1, None NA Classifications 50.55a RG 1.26 R4 3.3 Wind and Tornado None Loadings 3.3.1 'Wind Loadings 3.3.1 2007 10 CFR 50, App. A, GDC 2 None NA TVA will use recently issued RG 1.221 with regard to design basis hurricane and hurricane missiles. RG 1.221 is not referenced in the SRP Acceptance Criteria for this section.

3.3.2 Tornado Loadings 3.3.2 Tornado Loads 2007 10 CFR 50, App. A, GDC 2 None NA RG 1.76 R1 3.3.3 BOP Interface None 3.4 Water Level (Flood) None Design Page 9 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section - Key Issue(s)A Key Issue(s) StatusAdditional Information RG 1,70 (FSAR) Section Section Revision Acceptance Criteria 3.4.1 Flood Protection 3.4.1 Internal Flood 2007 10 CFR 50, App. A, GDC 2, 4 None NA Protection for Onsite RGs 1.29 R4 Equipment Failures 3.4.2 Analytical and Test 3.4.2 Analysis Procedures 2007 10 CFR 50, App. A, GDC 2 None NA Procedures 3.4.3 NSSS Interface None 3.4.3 BOP Interface None 3.5 Missile Protection None 3.5.1 Missile Selection and None Description None 3.5.1.1 Internally 2007 10 CFR 50, App. A, GDC 4 None NA TVA will use RG 1.115 R1 in lieu of R2.

Generated Missiles RG 1.115 R1, 1.117 R1 (Outside Containment)

None 3.5.1.2 Internally 2007 10 CFR 50, App. A, GDC 4 None NA Generated Missiles (Inside Containment)

None 3.5.1.3 Turbine Missiles 2007 10 CFR 50, App. A,GDC 4 None NA TVA will use RG 1.115 R1 in lieu of R2.

10 CFR 100, Subpart B RGs 1.115 R1, 1.117 R1 None 3.5.1.4 Missiles Generated 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA by Tornadoes and RG 1.76 R1 Extreme Winds None 3.5.1.5 Site Proximity 2007 10 CFR 100, Subpart B None NA Missiles (Except Aircraft) CFR 50, App. A, GDC 4 RG 1.91 R1 Page 10 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section ,Revision Acceptance Criteria Key Issue(s) Status None 3.5.1.6 Aircraft Hazards 2010 10 CFR 100, SubpartB For potential Preparing TVA will develop action plans for each requirement listed in 10 CFR 50, App. A, GDCs 3 & 4 aircraft accidents, summary 10 CFR 50.54(hh) and provide this plan to NRC.

RG 1.117 R1 BLN had discussion on construction security which permits issued will include prior to the 50.54(hh) effective date of requirements the final rule for related to consideration of security.

aircraft impact.

Thus, the rule does not apply to BLN. However, TVA will comply with the requirements of 10 CFR 50.54(hh).

3.5.2 Structures, Systems, 3.5.2 2007 10 CFR 50,App. A, GDCs 2& 4 None NA TVAwill use RG 1.115 R1 in lieu of R2.

and Components to be RGs 1.13 R2, 1.27 R2 (For Protected from Externally Comment), 1.115 R1 Gen Herated. IV, ie 1::-

3.5.3 Barrier Design 3.5.3 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA TVA will use AC! 318-71 Procedures RG 1.76 R1, 1.142 R2 3.5.4 NSSS Interface None 3.5.4 BOP Interface None 3.6 Protection Against None Dynamic Effects Associated with the Postulated Rupture of Piping Page 11 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan RG 1.70 (FSAR) Section Section Revision AcceptanceKey Isue() Additional Information F NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) 3.6.1 Postulated Piping 3.6.1 Plant Design for 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA Failures in Fluid Systems Protection Against BTP 3-3 (replaces SPLB 3-1) App.

Outside of Containment Postulated Piping Failures B in Fluid Systems Outside Containment 3.6.2 Determination of 3.6.2 Determination of 2007 10 CFR 50, App. A, GDC 4 None NA Break Locations and Rupture Locations and BTP 3-4 Dynamic Effects Associated Dynamic Effects with the Postulated Rupture Associated with the of Piping Postulated Rupture of Piping None 3.6.3 Leak-Before-Break 2007 10 CFR 50, App. A, GDC 4 LBB is factored TVA is preparing Evaluation Procedures into assessments a summary of BLN capability discussion of use to withstand new of spectra and response spectra consideration of and use will LOCA loads.

require NRC acceptance and consideration of AlloS 600 concerns.

3.7 Seismic Design None Page 12 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

Acceptance Criteria Key Issue(s) Status RG 1.70 (FSAR) Section Section Revision 3.7.1 Seismic Input 3.7.1 Seismic Design 2007 10 CFR 100, Subpart B Licensing basis Resolution of this Analysis features and criteria required to complete seismic Parameters 10 CFR 50, App. A, GDC 2; and of TVA position issue will address analysis of BLN structures and equipment include spatially App. S paper related to TVA position incoherent ground motion, equipment-structure interaction RGs 1.60 R1, 1.61 R1 design & paper regarding and potentially enriched spectra at lower frequencies.

analysis, and seismic analysis TVA will apply updated GMRS site specific spectra using consideration of of Category 1 2007 SRP approach in determining final positions for piping high frequency structures (TAC and commodities to address open issues as a result of content. No. 79276) and previously submitted position papers.

NRC SER dated 8/29/91.

3.7.2 Seismic System 3.7.2 2007 10 CFR 100, Subpart B Design basis WVA will review Chapter 19 includes a Seismic PRA.

Analysis 10 CFR 50, App. A, GDC 2; and earthquake using position paper App. S updated GMRS and NRC SER TVA will provide the information required by the March 12, RGs 1.92 R2, 1.122 R1 site specific dated 9/26/91 2012 NRC Request for Information (RFI) regarding seismic spectra (based against current reevaluations in accordance with the established on 1989 EPRI- requirements to timeframes.

SOG), with a determine minimum 0.1g appropriate earthquake, to position.

requirements of Appendix S, including updated soil investigation.

Licensing basis of TVA position paper related to seismic interactions dated 2/28/91 (TAC No.

79280)

Page 13 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.7.3 Seismic Subsystem 3.7.3 2007 10 CFR 50, App. A, GDC 2, App. S TVA will review Analysis 10 CFR 100, Subpart B Design basis position paper NUREG-1061 earthquake using and NRC SER updated GMRS dated 10/4/91 site specific against current spectra (based requirements to on 1989 EPRI- determine SOG), with a appropriate minimum O.1g position.

earthquake, to requirements of Appendix S, including updated soil investigation.

Licensing basis of TVA position paper involving structural adequacy of distributive systems dated 3/13/91 (TAC No.

79278) 3.7.4 Seismic 3.7.4 2007 10 CFR 20 None NA Instrumentation 10 CFR 50 App S RGs 1.12 R2, 1.166 RO 3.7.5 NSSS Interface None 3.7.5 BOP Interface None 3.8 Design of Category I None Structures Page 14 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

AcceptanceKey Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision 3.8.1 Concrete 3.8.1 2010 10 CFR 50, App A, GDCs 1,2, 4, None NA TVA will use ACI 318-71 and ASME Code of Record Containment 16, 50, 53, Apps. B and J, 50.44, 50.55a, RG 1.107, regarding cement grouting, is included in the RGs 1.7 R3, 1.35 R3, 1.35.1 R1, SRP Acceptance Criteria, but is not applicable to BLN.

1.90 Ri, 1.91 RI, 1.115 Ri, 1.136 R3 TVA will use RG 1.115 R1 in lieu of R2.

TVA will use the guidance contained in RG 1.216 RO relative to above design basis pressure loading.

3.8.2 Steel Containment 3.8.2 2010 10 CFR 50, App A, GDCs 1, 2, 4, None NA TVA will use ACI 318-71 and ASME Code of Record.

16, 50, Apps. B and J, 50.44, Revision of RG 1.84 will be consistent with requests to use 50.55a, Code Cases.

RGs 1.7 R3, 1.57 R1, 1.84, 1.193 TVA will use the guidance contained in RG 1.216 RO R3 relative to above design basis pressure loading.

3.8.3 Concrete and Steel 3.8.3 2010 10 CFR 50, App. A, GDCs 1,2, 4, None NA See 3.8.1 Internal Structures of Steel 16, 50, App B, 50.55a WVA will use RG 1.69 RO in lieu of R1.

or Concrete Containments RGs 1.57 R1, 1.69 RO, 1.136 R3, 1.142 R2, 1.143 R2, 1.160 R3, 1.199 RO 3.8.4 Other Seismic 3.8.4 2010 10CFR 50, App A,GDCs 1,2,4,5, None NA See 3.8.1 Category I Structures App B, .55a TVA will use RG 1.69 RO in lieu of RI.

RGs 1.60 R1, 1.61 R1, 1.69 RO, TVA will use RG 1.115 R1 in lieu of R2.

1.91 R1, 1.92 R2, 1.115 R1, 1.127 R1, 1.142 R2, 1.143 R2, 1.160 R3, 1.199 RO 3.8.5 Foundations 3.8.5 2010 10 CFR 50, App A, GDCs 1, 2, 4, None NA TVA will use ACI 318-71 5, .55a, .65 RGs 1.127 R1, 1.142 R2, 1.160 R3 3.8.6 NSSS Interface None Page 15 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Rev sion Acceptance Criteria Status 3.8.6 BOP Interface None 3.9 Mechanical Systems None and Components 3.9.1 Special Topics for 3.9.1 2007 10 CFR 50, App. A, GDCs 1,2, 14, None NA Mechanical Components 15, App. B, App. S 10 CFR 100, Subpart B 3.9.2 Dynamic Testing and 3.9.2 Dynamic Testing and 2007 10 CFR 50, App A, GDCs 1, 2, Qualification of TVA is Revision of RG 1.84 will be consistent with requests to use Analysis Analysis of Systems, 4,14, 15, App. B & App. S, .55a components for considering Code Cases.

Structures, and RGs 1.20, 1.61 R1, 1.68 R3, high frequency several testing Components 1.84,1.92 R2 motion options and For existing (legacy) equipment, TVA will use RG 1.20 R2.

mitigating For newly procured/ major modified equipment, TVA will devices use RG 1.20 R3.

3.9.3 ASME Code Class 1, 3.9.3 2007 10 CFR 50, App. A, GDCs 1, 2, 4, None NA TVA will not adopt the elements of Appendix A to SRP 2, and 3 Components, 14,15, App S, 55a Section 3.9.3 related to environmentally assisted fatigue.

Component Supports, and RGs 1.124, 1.130 TVA will use Code of Record and applicable code cases for Core Support Structures existing (legacy) equipment, and current code, with applicable code cases, for newly procured equipment.

For existing (legacy) equipment, TVA will use the following:

RGs 1.124 R1, 1.130 R1 For newly procured/major modified equipment, WVA will use the following: RGs 1.124 R2, 1.130 R2 WVA will not adopt RG 1.207 related to the effects of environment on fatigue analyses for new reactors.

3.9.4 Control Rod Drive 3.9.4 2007 10 CFR 50, App A, GDCs 1, 2,14, None NA Systems 26, 27, 29, .55a RG 1.26 R4 3.9.5 Reactor Pressure 3.9.5 2007 10 CFR 50.55a, 10 CFR 50, App None NA For existing (legacy) equipment, TVA will use RG 1.20 R2.

Vessel Internals A, GDCs 1,2, 4, 10: .55a For newly procured/major modified equipment,TVA will RG 1.20 use RG 1.20 R3.

Page. 16 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Keysus) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 3.9.6 Inservice Testing of 3.9.6 Functional Design, 2007 10 CFR 50.55a (including None [NA GL 95-07, Pressure Locking and Thermal Binding of Pumps and Valves Qualification, and 50.55a(b)-(g)), 10 CFR,50, App A, Safety-Related Power-Operated Gate Valves Inservice Testing GDCs 1, 2, 4,14,15, 37, 40, 43, Programs for Pumps, 46, 54, App. B Valves, and Dynamic RGs 1.174 R2, 1.175 RO, 1.192 RO Restraints 3.9.7 NSSS Interface 3.9.7 Risk-Informed 1998 10 CFR 50.55a, 50.59, and App. B None NA Inservice Testing RGs 1.174 R2, 1.175 RO None 3.9.8 Risk-Informed 2003 10 CFR 50.55a and Appendix A None NA Inservice Inspection of RGs 1.174 R2, 1.178 R1 Piping 3.10 Seismic Qualification 3.10 Seismic and Dynamic 2007 10 CFR 50, App. A, GDCs 1, 2, 4, Position paper on TVA will review TVA position will include approach to qualification of of Seismic Category I Qualification of Mechanical 14, 30, App. B & S seismic position paper equipment subjected to high frequency content.

Instrumentation and and Electrical Equipment 10 CFR 100, Subpart B qualification of and NRC SER Electrical Equipment RGs 1.61 R1, 1.92 R2, 1.97 R3, equipment dated dated 10/10/91 TVA will use RG 1.97 R3 in lieu of R4.

1.100 8/28/91 (TAC No. against current 79279) requirements to determine For existing (legacy) equipment, TVA will use RG 1.100 appropriate RI.

position. For newly procured/major modified equipment, TVA will use RG 1.100 R3.

3.10.1 Seismic Qualification None Criteria 3.10.2 Methods and None Procedures for Qualifying Electrical Equipment and Instrumentation 3.10.3 Methods and None Procedures of Analysis or Testing of Supports of Electrical Equipment and _I Page 17 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Ise Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria AdtolIfrStatus Instrumentation 3.10.4 Operating License None Review 3.10.5 NSSS Interface None 3.11 Environmental Design 3.11 Environmental 2007 10 CFR 50.49, 50.65, 50.67, App None NA 10 CFR 50.67 does not apply to BLN. It is included to of Mechanical and Qualification of Mechanical A, GDCs 1, 2, 4, 23 and App. B highlight that BLN intends to utilize the Alternative Source Electrical Equipment and Electrical Equipment RGs 1.40,1.63,1.73 RO, 1.89, Term methodology.

1.97 R3, 1.156 R1, 1.158 R0, 1.160 R3, 1.180, 1.183 RO, TVA will use RG 1.97 R3 in lieu of R4.

1.211 R0 NUREG10588, 0737, lI.B.2 For existing (legacy) equipment, TVA will use the following:

RGs 1.40 RO, 1.63 R2, 1.89 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.40 R1, 1.63 R3, 1.89 R1, 1.180 R1 Equipment procured by TVA as of Aug. 31, 1991 will be qualified to at least the standards of NUREG-0588, Category II.

Equipment procured after Aug. 31, 1991 will be qualified to the standards of NUREG-0588, Category I unless "sound reasons to the contrary" (as defined in RG 1.89) exist.

Where "sound reasons to the contrary" exist, qualification will be at least to the standards of NUREG-0588, Category II.

3.11.1 Equipment None Identification and Environmental Conditions Page 18 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information Section Revision Acceptance Criteria Status 3.11.2 Qualification Tests None and Analyses 3.11.3 Qualification Test None Results 3.11.4 Loss of Ventilation None 3.11.5 Estimated Chemical None and Radiation Environment 3.11.6 NSSS Interface None None 3.12 ASME Code Class 1, 2007 10 CFR 50.55a, App A, GDCs 1, 2, Position paper on TVA will review TVA will use Code of Record. Revision of RG 1.84 will be 2, and 3 Piping Systems, 4, 14, 15 and App. S, structural position paper consistent with requests to use Code Cases.

Piping Components and RG 1.84 analysis methods and NRC SER TVA will not adopt the elements of Appendix A to SRP their Associated Supports for piping, tubing dated 10/4/91 Section 3.9.3 related to environmentally assisted fatigue.

and supports against current TVA will not adopt RG 1.207 related to the effects of dated 3/13/91 requirements to environment on fatigue analyses for new reactors.

(TAC No. 79277) determine appropriate position.

Page 19 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key I Key Issue(s) Additional Information Section Revision Acceptance Criteria Status None 3.13 Threaded Fasteners - 2007 10 CFR 50.55a, App A, GDCs 1,4, None NA TVA will use Code of Record for existing (legacy)

ASME Code Class 1,2, 14, 30, 31, Apps. B, and & G equipment and current code for newly procured equipment.

and 3 RG 1.37 For existing (legacy) equipment, TVA will use RG 1.37 RO.

For newly procured/major modified equipment, TVA will use RG 1.37 Ri.

IEB 89-02, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Preloaded Bolting in Anchor Darling Model $350W Swing Check Valves or Valves of Similar Nature.

GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants None BTP 3-1 Classification of NA to BLN - BWRs only Main Steam Components Other than the Reactor Coolant Pressure Boundary for BWR Plants None BTP 3-2 Classification of NA to,BLN - BWRs only BWR/6 Main Steam and Feedwater Components Other than the Reactor Coolant Pressure Boundary None BTP 3-3 Protection 2007 10 CFR 50, App. A, GDCs 2 & 4 None NA TVA will use Appendix B to BTP 3-3.

Against Postulated Piping RGs 1.26 R4, 1.29 R4 Failures in Fluid Systems Outside Containment Page 20 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG0800 (SRP) 1 SRP SRP Section Key issue(s) Key Issue(s)

Status Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria None BT 3-4 Postulated 2007 10 CFR 50, App. A, GOC 4 None NA Rupture Locations in Fluid RG 1.11 R1 System Piping Inside and Outside Containment Page 21 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) 1 SRP [ SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key__ssues A nStatus Chapter 4 - Reactor

4. Reactor None 4.1 Summary Description None 4.2 Fuel System Design 4.2 2007 10 CFR 50, App. A, GDCs 2,10,27 None NA 10 CFR 50.67 does not apply to BLN. It is included to 35, 50.34, .46, .67, App.K highlight that BLN intends to utilize the Alternative Source 10 CFR 100, Subpart B Term methodology.

NUREG-75/077, -0085, -0303, - TVA will use an Appendix K compliant methodology in lieu 0308, -0401, -0418, -0609, -0630, of the RG 1.157 best estimate methodology referenced in

/CR-1018, /CR-1019, /CR-1020, this SRP section.

/CR-1 380, -1883, & /CR-6534 RGs 1.4 R2, 1.25 RO, 1.60 R1, 1.77 RO, 1.126 R2, 1.183 RO, 1.196 R1 4.2.1 Design Bases None 4.2.2 Description and None Design Drawings 4.2.3 Design Evaluation None 4.2.4 Testing and None Inspection Plan 4.3 Nuclear Design 4.3 2007 10 CFR 50, App. A, GDCs 10, 11, None NA 12, 13, 20, 25, 26, 27, & 28 RGs 1.77 RO, 1.126 R2 4.3.1 Design Bases None 4.3.2 Description None 4.3.3 Analytical Methods None 4.3.4 Changes None Page 22 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan RG 1.70 (FSAR) Section NUREG 0800 (SRP)

Section SRP Revision SRP Section

-Acceptance Criteria 1Ky Iss() Key Issue(s)

Status Additional Information 4.4 Thermal and Hydraulic 4.4 2007 10 CFR 50, App. A, GDCs 10 & 12 None NA TMI Action Item - II.K.2.13, Thermal Mechanical Report Design NUREG-0737 & -1449 (Reactor Vessel)

RGs 1.68 R3, 1.133 RI 4.4.1 Design Bases None 4.4.2 Description of None Thermal and Hydraulic Design of the Reactor Core 4.4.3 Description of the None Thermal and Hydraulic Design of the Reactor Coolant System 4.4.4 Evaluation None 4.4.5 Testing and None Verification 4.4.6 Instrumentation None Requirements 4.5 Reactor Materials None 4.5.1 Control Rod Drive 4.5.1 Control Rod Drive 2007 10 CFR 50, App. A, GDCs 1, 14, & None NA For existing (legacy) equipment, TVA will use RG 1.44 RO.

System Structural Materials Structural Materials 26, 50.55a For newly procured/major modified equipment, TVA will RG 1.44 use RG 1.44 RI.

4.5.2 Reactor Internals 4.5.2 Reactor Internal and 2007 10 CFR 50, App. A, GDC 1, None NA For existing (legacy) equipment, TVA will use RGs 1.31 R1 Materials Core Support Structure 50.55a and 1.44 R0.

Materials NUREG-1823 For newly procured/major modified equipment, TVA will RGs 1.31, 1.44, 1.84 use RGs 1.31 R3 and 1.44 RI.

Revision of RG 1.84 will be consistent with requests to use I I Code Cases.

4.6 Functional Design of 4.6 Functional Design of 2007 10 CFR 50, App. A, GDCs 4, 23, None NA GL 93-04, Rod Control System Failure and Withdrawal of Reactivity Control Systems Control Rod Drive System 25, 26, 27, 28, 29, 50.62(c)(1), Rod Control Cluster Assemblies, 10 CFR 50.54(f)

I _.62(c)(2)

Page 23 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptan ce Criteria Keyo)Status 4.6.1 Information for CRDS None 4.6.2 Evaluations of the None CRDS 4.6.3 Testing and None Verification of the CRDS 4.6.4 Information for None Combined Performance of Reactivity Systems 4.6.5 Evaluations of None Combined Performance None BTP 4-1 Westinghouse Constant Axial Offset Control (CAOC)

Page 24 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revis on Acceptance Criteria Key Issue(s) Status Chapter 5 - Reactor Coolant System and Connected Systems

5. Reactor Coolant System None and Connected Systems 5.1 Summary Description None 5.1,1 Schematic Flow None Diagram 5.1,2 Piping and None Instrumentation Diagram 5.1.3 Elevation Drawing None 5.2 Integrity of Reactor None Coolant Pressure Boundary 5.2.1 Compliance with None Codes and Code Cases None 5.2.1.1 Compliance with 2007 10 CFR 50.55a None NA the Codes and Standards 10 CFR 50, App. A, GDC 1 Rule, 10 CFR 50.55a RG 1.26 R4 None 5.2.1.2 Applicable Code 2007 10 CFR 50, App. A, GDC 1 None NA TVA will use code cases originally referenced per Code of Cases 10 CFR 50.55a Record for existing (legacy) equipment and currently RGs 1.84,1.147 approved code cases for newly installed equipment.

Revision of RG 1.84 and 1.147 will be consistent with requests to use Code Cases.

Page 25 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan I NUREG 0800 (SRP) SRP SRP Section 1 s Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section RevAcceptance CriteriasfnKey Issue(s) Status 5.2.2 Overpressure 5.2.2 2007 10 CFR 50, App. A, GDCs 1, 15, None NA TVA will use the existing code of record plus TMI Protection 30, &31, 50.55a qualification tests. Should new equipment be required, it RG 1.84 will be purchased to the latest code which has received NUREG-0737, I1.K.3.3, Il.D.1, & regulatory approval at the time of order, and will be ll.D.3, NUREG 1430 reconciled to the original code of record.

GLs 82-16, and 90-06 Revision of RG 1.84 will be consistent with requests to use Code Cases.

TMI Action Item - I1.K.2.14, Lift Frequency of PORVs and SVs TMI Action Item - II.K.3.1, Auto PORV Design and Testing TMI Action Item - II.K.3.2, Report on PORV Failures TMI Action Item - II.K.3.7, Evaluation of PORV Opening Probability 5.2.3 Reactor Coolant 5.2.3 2007 10 CFR 50, App. A, GDCs 1, 4, 14, Need to address TVA is preparing Plan to implement Alloy 600 program to mitigate PWSCC Pressure Boundary 30 & 31; App. B, App. G, 50.55a concerns for a discussion of consistent with NEI initiative NEI 03-08. Will also consider Materials RGs 1.31, 1.34, 1.36 RO, 1.37, PWSCC of Alloy mitigating NUREG 1823 & NRC Order EA-03-009.

1.43, 1.44, 1.50, 1.71, 1,84 600 components strategy for

& dissimilar metal PWSCC of Alloy For existing (legacy) equipment, TVA will use the following:

welds (DMW) 600 components RGs 1.31 R1, 1.34 RO, 1.37 RO, 1.43 RO, 1.44 RO, 1.50 RO, and 0MW 41.71 R0 For newly procured/major modified equipment, TVA will use the following: RGs 1.31 R3, 1.34 R1, 1.37 R1, 1.43 R1, 1.44 R1, 1.50 R1, 1.71 R1 Revision of RG 1.84 will be consistent with requests to use Code Cases.

5.2.4 Inservice Inspection 5.2.4 Reactor Coolant 2007 10 CFR 50, App. A, GDC 32, 50.2, See 5.2.3 See 5.2.3 Revision of RG 1.147 will be consistent with requests to and Testing of Reactor Pressure Boundary 50.55a use Code Cases.

Coolant Pressure Boundary Inservice Inspection and RG 1.147 Testing GL 88-05 Page 26 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section SectionaRev Criteri onSKeytIssueas)tAdditionaluInfor 5.2.5 Detection of Leakage 5.2.5 Reactor Coolant 2007 10 CFR 50, App. A, GDCs 2, 30 See 5.2.3 See 5.2.3 TVA will use RG 1.45 RO with regard to RCS leak detection Through Reactor Coolant Pressure Boundary RGs 1.29 R4, 1.45 RO and monitoring as its design basis, and make a good faith Pressure Boundary Leakage Detection effort to adopt the good practices identified in RG 1.45 R1.

5.2.6 NSSS Interface None 5.3 Reactor Vessels None 5.3.1 Reactor Vessel 5.3.1 2007 10 CFR 50, App. A, GDCs 1,4, 14, See 5.2.3 See 5.2.3 See 5.2.3 for Alloy 600.

Materials 30, 31, 32, App. B, G, H, 50.55a, TVA will retain the 1981 SRP and will use RG 1.99 R2 with

.60, .61 the exception of Section C.3.

RGs 1.31 R1, 1.34, 1.37, 1.43, For existing (legacy) equipment, TVA will use the following:

1.44,1.50,1.65,1.99 R2, RGs 1.34 RO, 1.37 R0 1.43 RO, 1.44 RO, 1.50 RO 1.161 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.34R1, 1.37 R1, 1.43 R1, 1.44 R1, 1.50 R1 TVA will use RG 1.65 RO for existing studs and RG 1.65 RI for stud lubricant detrimental materials.

TVA will use RG 1.31 R1 in lieu of R3.

5.3.2 Pressure- 5.3.2 Pressure- 2007 10 CFR 50, App. A, GDCs 1, 14, TVA will use RG 1.99 R2 with the exception of Section C.3 Temperature Limits Temperature Limits, 31. 32, App. G. 50.55a..60..61, Upper-Shelf Energy, and RGs 1.99 R2, 1.161 RO Pressurized Thermal Shock 5.3.3 Reactor Vessel 5.3.3 2007 10 CFR 50, App. A, GDCs 1,4, See 5.2.3 See 5.2.3 TVA will use RG 1.99 R2 with the exception of Section C.3.

Integrity 14, 30, 31, 32, App. B, App. G, H, 50.55a, .60, .66 RG 1.99 R2 5.4 Component and 5.4 Reactor Coolant None None None Subsystem Design System Component and Subsystem Design Page 27 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Key Issue(s) Additional Information 5.4.1 Reactor Coolant None Pumps None 5.4.1.1 Pump Flywheel 2010 10CFR 50, App. A, GDCs 1,4,10 None None Integrity (PWR) 50.55a(a)(1) & (f)

RG 1.14 R1 5.4.2 Steam Generators None None 5.4.2.1 Steam Generator 2007 10 CFR 50, App. A, GDCs 1, 4, . None None For existing (legacy) equipment, TVA will use the following:

Materials 14,15,30,31, App. B, App. G, RGs 1.34 RO, 1.37 RO, 1.43 R0, 1.44 R0, 1.50 RO, 1.71 RO 50.36, 55a(b), (c), (d), & (e) For newly procured/major modified equipment, TVA will RGs 1.31 R3, 1.34,1.36 RO, 1.37, use the following: RGs 1.34 R1, 1.37 R1, 1.43 R1, 1.44 R1, 1.43, 1.44, 1.50,1.71, 1.84 1.50 R1, 1.71 R1 BTP 5-1 Revision of RG 1.84 will be consistent with requests to use NUREG - 1430 Code Cases.

Replacement steam generator tubing will be Alloy 690.

None 5.4.2.2 Steam Generator 2007 10 CFR 50, App. A, GDC 32, App. See 5.4.2.1 Open The Steam Generator Program for BLN will meet Revision Program B, 50.36, .55a, .65 2 of 'EPRI-Steam Generator Program Administrative RG 1.121 R0 Procedures" and Revision 2 of NEI 97-06, "Steam NUREG-1430 Generator Program Guidelines".

TMI Action Item - I1.K.2.15, Effects of Slug Flow on OTSGS 5.4.3 Reactor Coolant None Piping 5.4.4 Main Steam Line Flow None Restrictions 5.4.5 Main Steam Line None Isolation System 5.4.6 Reactor Core 5.4.6 Reactor Core NA to BLN, BWRs only Isolation Cooling System Isolation Cooling System (BWR)

Page 28 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SR~P SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 5.4.7 Residual Heat 5.4.7 Residual Heat 2010 10 CFR 50, App. A, GDCs 2, 4, None None BLN is a Class 2 plant relative to implementing the Removal System Removal (RHR) System 5,19, & 34, 10 CFR 50.34 requirements of BTP 5-4.

RGs 1.29 R4, 1.82 R4 Regarding RG 1.82, the BLN design credits some small BTP 5-4 degree of containment accident pressure to ensure pump NUREG- 0737, III.D.1.1 net positive suction head (NPSH) requirements are met during a design basis loss-of-coolant-accident (LOCA).

5.4.8 Reactor Water 5.4.8 Reactor Water NA to BLN, BWRs only Cleanup System Cleanup System (BWR) 5.4.9 Main Steam Line and None Feedwater Piping 5.4.10 Pressurizer None 5.4.11 Pressurizer Relief 5.4.11 Pressurizer Relief 2010 10 CFR 50, App, A, GDCs 2, 4 None None The reactor coolant drain tank performs the pressurizer Discharge System Tank RG 1.29 R4 relief function and will satisfy Code Case N-770.

5.4.12 Valves 5.4.12 Reactor Coolant 2007 10 CFR 50, App. A, GDCs 1, 14, None None TVA will conform with the 1981 SRP Acceptance Criteria System High Point Vents 17, 19, 30, 32, 34, 36, App. B, for existing (legacy) equipment.

50.34(f), 44(c), .46, .46a & (b), .49,

.55a For existing (legacy) equipment, TVA will use RG 1.100 RGs 1.92 R2, 1.100 R1.

For newly procured/major modified equipment, TVA will use RG 1.100 R3.

TMI Action Item - Il.B.1, Reactor-coolant-system vents.

5.4.13 Safety and Relief 5.4.13 Isolation Condenser NA to BLN, BWRs only Valves System (BWR) 5.4.14 Component None Supports Page 29 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section [Revision Acceptance Criteria Key Issue(s) Status None BTP 5-1 Monitoring of 2007 10 CFR 50.71 None None For steam generator secondary side water chemistry, BLN Secondary Side Water will meet the latest revision of "EPRI PWR Secondary Chemistry in PWR Steam Water Chemistry Guidelines" and for primary / secondary Generators leakage compliance will meet the latest revision of "EPRI PWR Primary / Secondary Leak Guidelines."

None BTP 5-2 2007 10 CFR 50, App. G None None Overpressurization RGs 1.26 R4, 1.29 R4 Protection of Pressurized-Water Reactors While Operating at Low Temperatures None BTP 5-3 Fracture 2007 10 CFR. 50, App. G, App. H None None Toughness Requirements ASME Code,Section III 10 CFR 50.61 None BTP 5-4 Design 2007 10 CFR 50, App. A, GDC 1 - 5 None None BLN is a Class 2 plant relative to implementing the Requirements of the IEEE 338-1987 requirements of BTP 5-4.

Residual Heat Removal RG 1.22 RO, 1.33 R2, 1.68 R3 System Page 30 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status Chapter 6 - Engineered Safety Features

6. Engineered Safety None Features 6.1 Engineered Safety None Feature Materials 6.1.1 Metallic Materials 6.1.1 Engineered Safety 2007 10 CFR 50, App. A,GDCs 1,4,14, None NA For existing (legacy) equipment, TVA will use the following:

Features Materials 31,35, 41, 55a, App. B Criteria IX, RGs 1.31 R11 1.37 RO, 1.44 RO, 1.50 RO, 1.71 RO XIII For newly procured/major modified equipment, TVA will RGs 1.7 R3, 1.31, 1.36 RO, 1.37, use the following: RGs 1.31 R3, 1.37 R1, 1.44 R1, 1.50 R1, 1.44,1.50,1.71,1.84 1.71 R1.

BTP 6-1 Revision of RG 1.84 will be consistent with requests to use ASME Code Code Cases.

6.1.2 Organic Materials 6.1.2 Protective Coating 2007 10 CFR 50, App. B None NA GL 98-04, Potential for Degradation of the ECCS and the Systems (Paints) - RG 1.54 R2 Containment Spray System After a LOCA Because of Organic Materials ASTM D5144-00, ASTM D3911-03 Construction and Protective Coating Deficiencies and Foreign Material in Containment.

6.2 Containment Systems None 6.2.1 Containment 6.2.1 None None NA Functional Design None 6.2.1. 1.A PWR Dry 2007 10 CFR 50.34(f)(3)(v)(A)(1), .46, None NA Containments, Including App. K, I.D.2, App. A, GDCs 4,13, Subatmospheric 16, 38, 50, 64 Containments BTP 7-10 Page 31 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Key Issue(s)

Kssue~s Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status NUREG-0737, Item II.F.1 None 6.2.1.1..B Ice Condenser NA to BLN - Ice Condenser plants only Containments None 6.2.1. 1.C Pressure- NA to BLN - BWRs only Suppression Type BWR Containments None 6.2.1.2, Subcompartment 2007 10 CFR 50, App. A, GDCs 4 & 50 None NA Analysis Section 3.2 of NUREG-0609 None 6.2.1.3 Mass and Energy 2007 10 CFR 50, App. A, GDC 50, App. None NA Release Analysis for K Postulated Loss-of-Coolant Accidents (LOCAs)

None, 6.2.1.4 Mass and Energy 2007 10 CFR 50, App. A, GDC 50 None NA Release Analysis for Postulated Secondary System Pipe Ruptures None 6.2.1.5 Minimum 2007 10 CFR 50.46(a)(1)(i), .46(a)(1)(ii), None NA TVA will use an Appendix K compliant methodology in lieu Containment Pressure .47(b)(1), App. K of the RG 1.157 best estimate methodology referenced in Analysis for Emergency BTP 6-2 this SRP section.

Core Cooling System Performance Capability Studies 6.2.2 Containment Heat 6.2.2 2007 10 CFR 50, App. A, GDCs 38, 39, None NA See 6.1.1 for ASME Code.

Removal Systems 40, .46(b)(5), Regarding RG 1.82, the BLN design credits some small RGs 1.82 R4, 1.174 R2 degree of containment accident pressure to ensure pump I __Innet positive suction head (NPSH) requirements are met Page 32 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section 1 Key Issue(s)

Status Additional Information Section Revision Acceptance Criteria Key Issue(s)

RG 1.70 (FSAR) Section during a design basis loss-of-coolant-accident (LOCA).

6.2.3 Secondary 6.2.3 2007 10 CFR 50, App. A, GDCs 4, 16, None NA For existing (legacy) equipment TVA will use RG 1.52 RI.

Containment Functional 43, App. J For newly procured/major modified equipment TVA will use Design RG 1.52 RG 1.52 R4.

BTPs 6-2, 6-3 6.2.4 Containment Isolation 6.2.4 2007 10 CFR 50, App. A, GDCs 1,2,4, None NA System 16, 54, 55, 56, 57, App. K,

.63(a)(2)

RGs 1.11 R1, 1.26 R4, 1.29 R4, 1.141 R1, 1.155 R0 BTP 6-4 NUREG-0737, I1.E.4.2 6.2.5 Combustible Gas 6.2.5 2007 10 CFR 50.44, .44(c)(5), App. A, None NA TVA will use the guidance contained in RG 1.216 R0 Control in Containment GDCs 5, 41,42, 43, relative to above design basis pressure loading.

RG 1.7 R3 6.2.6 Containment Leakage 6.2.6 2007 10 CFR 50, App A, GDCs 52, 53, None NA Testing 54, App. J 10 CFR !00, Subpat B RG 1.163 RO BTP 6-3 None 6.2.7 Fracture Prevention 2007 10 CFR 50, App. A, GDCs 1, 16,. None NA See 6.1.1 for ASME Code of Containment Pressure 51 Boundary ASME Section III Page 33 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status A 6.3 Emergency Core 6.3 2007 10 CFR 50.46, 50.63, App A, None NA Regarding RG 1.1, the BLN design credits some small Cooling System GDCs 2, 4, 5, 17, 27, 35, 36, 37, degree of containment accident pressure to ensure pump App. K net positive suction head (NPSH) requirements are met RGs 1.1 RO, 1.29 R4, 1.47 R1 during a design basis loss-of-coolant-accident (LOCA).

NUREG- 0737, ll.D.3, II.F.2, III.D.1.1, I1.K.3.17 TVA will use an Appendix K compliant methodology in lieu of the RG 1.157 best estimate methodology referenced in this SRP.section, GL 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems TMI Action Item - II.K.1.5, Review of ESF Valves TMI Action Item - II.K.1.10, Operability Status TMI Action Item - II.K.1.20, Prompt Manual Reactor Trip TMI Action Item - II.K.1.21, Auto SG Anticipatory Reactor Trip 6.3.1 Design Bases None 6.3.2 System Design None 6.3.3 Performance None Evaluation 6.3.4 Tests and Inspections None 6.3.5 Instrumentation None Requirements Page 34 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) mation Key Issue(s) StatusAdditional Infor RG 1.70 (FSAR) Section Section Revision Acceptance Criteria 6.4 Habitability Systems 6.4 Control Room 2007 10 CFR 50.2,.67, App. A, GDCs 4, None NA 10 CFR 50.67 does not apply to BLN. It is included to Habitability System 5,19 highlight that BLN intends to utilize the Alternative Source RGs 1.52, 1.78 R1, 1.183 R0, Term methodology.

1.196 R1, 1.197 RO For existing (legacy) equipment TVA will use RG 1.52 R1.

NUREG - 0737, II1.D.3.4 For newly procured/major modified equipment TVA will use RG 1.52 R4.

6.4.1 Design Basis None 6.4.2 System Design None 6.4.3 System Operational None Procedures 6.4.4 Design Evaluations None 6.4.5 Testing and None Inspection 6.4.6 Instrumentation None Requirement 6.5 Fission Product Removal and Control Systems 6.5.1 Engineered Safety 6.5.1 ESF Atmosphere 2010 10 CFR 50, App. A, GDCs 19, 41, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Feature (ESF) Filter Cleanup Systems 42, 43, 61, 64 For newly procured/major modified equipment WVA will use Systems RG 1.52 RG 1.52 R4.

6.5.2 Containment Spray 6.5.2 Containment Spray 2007 10 CFR 50, App. A, GDCs 41,42, None NA Systems as a Fission Product 43 Cleanup System ANSI/ANS 56.5 Page 35 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)A tna or Key Issue(s) StatusAdditional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria 6.5.3 Fission Product 6.5.3 Fission Product 2007 10 CFR 50, App. A,'GDCs 19, 41, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Control Systems Control Systems and 42, 43 For newly procured/major modified equipment TVA will use Structures 10 CFR 100, Subpart B RG 1.52 R4.

RG 1.52 6.5.4 Ice Condenser as a 6.5.4 NA to BLN - Ice Condenser plants only Fission Product Cleanup System None 6.5.5 Pressure NA to BLN - BWRs only Suppression Pool as a Fission Product Cleanup System 6.6 Inservice Inspection of 6.6 Inservice Inspection 2007 10 CFR 50.55a, App. A, GDCs 36, None NA Class 2 and 3 Components and Testing of Class 2 and 37, 39, 40, 42, 43, 45, & 46 3 Components ASME Sections IIIand XI 6.6.1 Components Subject None to Examination 6.6.2 Accessibility None 6.6.3 Examination None Techniques and Procedures 6.6.4 Inspection Intervals None 6.6.5 Examination None Categories and Requirements 6.6.6 Evaluation of None Examination Results 6.6.7 System Pressure None Tests Page 36 of 91 TVA Letter dated October 10, 2012 Table I - BILN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Ise Key Issue(s) Additional Information Acceptance Criteria Ke Status RG 1.70 (FSAR) Section Section Revision 6.6.8 Augmented Inservice None Inspection to Protect Against Postulated Piping Failures 6.7 Main Steam Isolation 6.7 Main Steam Isolation NA to BLN - BWRs only Valve Leakage Control Valve Leakage Control System System (BWR) 6.7.1 Design Bases None 6.7.2 System Description None 6.7.3 System Evaluation None 6.7.4 Instrumentation None Requirements 6.7.5 Inspection and None Testing None BTP 6 pH For None None NA Emergency Coolant Water for Pressurized Water Reactors None BTP 6 Minimum None None NA Containment Pressure Model for PWR ECCS Performance Evaluation None BTP 6 Determination of 2007 10 CFR 50, Appendix J, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Bypass Leakage Paths in RGs 1.26 R4, 1.52,1.96 R1 For newly procured/major modified equipment TVA will use Dual Containment Plants RG 1.52 R4.

None BTP 6 Containment 2007 10 CFR 50, App A, GDCs 54 and None NA Purging During Normal 56, App. K, Plant Operations 10 CFR 100, Subpart B Page 37 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key I Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria K ssue~s) Status None BTP 6 Currently the 2007 10 CFR 50.46 None NA Responsibility of Reactor Systems Piping From the RWST (or BWST) and Containment Sump(s) to the Safety Injection Pumps Page 38 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key issue(s) Status Additional Information Chapter 7 - Instrumentation and Controls

7. Instrumentation and None Controls None 7.0 Instrumentation and 2010 None Digital I&C TVA will provide TVA is aware of Interim Staff Guidance regarding digital Controls - Overview of an updated instrumentation and controls, and will consider this Review Process position on the guidance in the BLN final design.

licensing basis for Digital I&C and present an overall approach.

None Appendix 7.0-A Review 2007 See 7.2 - 7.9. See 7.0 See 7.0 TVA will identify specific requirements to be met in Process for Digital subsequent sections.

Instrumentation and Control Systems 7.1 Introduction 7.1 Instrumentation and 2007 See 7.2 - 7.9. See 7.0 See 7.0 TVA will identify specific requirements to be met in Controls - Introduction subsequent sections.

7.1.1 Identification of None Safety-Related Systems 7.1.2 Identification of Safety None Criteria None 7.1-Table 7-1 Regulatory 2007 See 7.2 - 7.9. See 7.0 See 7.0 TVA will identify specific requirements to be met in Requirements, subsequent sections.

Acceptance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety Page 39 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) St None Appendix 7.1-A 2007 See 7.2 - 7.9. See 7.0 See 7.0 TVA will identify specific requirements to be met in Acceptance Criteria and subsequent sections.

Guidelines for Instrumentation and Controls Systems Important to Safety None Appendix 7.1-B Guidance 2007 IEEE-279-1971 See 7.0 See 7.0 for Evaluation of Conformance to IEEE Std 279 None Appendix 7.1-C Guidance 2007 IEEE-603-1991 See 7.0 See 7.0 for Evaluation of Conformance to IEEE Std 603 None Appendix 7.1-D Guidance 2007 IEEE-7-4.3.2-2003 See 7.0 See 7.0 for Evaluation of the Application of IEEE 7-4.3.2 7.2 Reactor Trip System 7.2 2007 10 CFR 50, App. A, GDC 1, 2, 4, See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-10, 13, 15,19, 20, 21, 22, 23, 24, 1971.

25, 29, For newly procured/major modified equipment, TVA will i0 CFR 50.55a(a)(1), .55a(h)(2) use IEEE 603-1991, except for the TELEPERM XS system RGs 1.22 RO, 1.47 R1, 1.53 R2, which will satisfy the requirements of IEEE 603-1998.

1.62 R1, 1.75, 1.105 R3, 1.118 R3, 1.151, 1.152 R3, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, For existing (legacy) equipment, TVA will use the following:

1.172 RO, 1.173 RO, 1.180, 1.204, RGs 1.75 R2, 1.151 RO 1.209 For newly procured/major modified equipment, TVA will BTPs 7-3, 7-5, 7-8, 7-9, 7-11,7-12, use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 7-13, 7-14,7-17,7-18,7-19,7- RO, 1.209 RO 21 For previously approved digital platforms (i.e., those with NUREG-0737, I.D.3, Il.K.2.10 NRC SERs for vendor topical reports), the use of the applicableRegulatoryGuidesapaRuoG ens Standards, and Page 40 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Kee e Issues) sue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there are approved vendor topical reports available to support the review.

GL 83-28, Required Actions Based on Generic Implications of Salem ATWS Events 7.2.1 Description None 7.2.2 analysis None 7.2.3 NSSS Interface None Page 41 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 7.3 Engineered-Safety- 7.3 Engineered Safety 2007 10 CFR 50, App. A, GDC 1, 2, 4, 10, 13, 15, 16, 19, 20, 21, 22, 23, See 7.0 See 7.0 1971.existing (legacy) equipment, WA will use IEEE 279-For Feature Systems Features Systems 24, 29, 33, 34, 35, 38, 41, 44, For newly procured/major modified equipment, TVA will

.55a(a)(1), .55a(h)(2) use IEEE 603-1991, except for the TELEPERM XS system RGs 1.22 RO, 1.47 R1, 1.53 R2, which will satisfy the requirements of IEEE 603-1998.

1.62 R1, 1.75, 1.105 R3, 1.118 R3, 1.151, 1.152 R3, 1.168 R1, 1.169 RO, 1.170 RO, 1.171 RO, For existing (legacy) equipment, TVA will use the following:

1.172 R0, 1.173 RO, 1.180, 1.204, RGs 1.75 R2, 1.151 RO 1.209 For newly procured/major modified equipment, TVA will BTP 7-3, 7-4, 7-6, 7-8, 7-11, 7-12, use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 7-13, 7-14, 7-17, 7-18, 7-19, 7-21 RO, 1.209 RO NUREG-0737, I.D.3, II.E.1.2, For previously approved digital platforms (i.e., those with II.E.4.2 NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there are approved vendor topical reports available to support the review.

GL 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)

GL 96-01, Testing Of Safety-Related Logic Circuits 7.3.1 Description None 7.3.2 Analysis None Page 42 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan R NUREG 0800 (SRP) SRP n SRP Section KKey Issue(s)

Seto -~ vso Acceptance Criteria Status RG17FA)Section Section Revision Acetaceyien Statuss)Additional Information 7.4 Systems Required for 7.4, Safe Shutdown 2007 10 CFR 50, App. A, GDC 1, 2,4, See 7.0 See 7.0 For existing (legacy) equipment, TVA Will use IEEE 279-Safe Shutdown Systems 13,19, 24, 34, 35, 38, 1971.

50.55a(a)(1 ),50.55a(h) For newly procured/major modified equipment, TVA will RGs 1.53 R2, 1.75, 1.105 R3, use IEEE 603-1991, except for the TELEPERM XS system 1.118 R3, 1.151, 1.152 R3, which will satisfy the requirements of IEEE 603-1998.

1.168 R1, 1.169 R0, 1.170 R0, 1.171 RO, 1.172 R0, 1.173 RO, 1.180, 1.189 R2, 1.204, 1.209 For existing (legacy) equipment, WVA will use the following:

BTPs 7-11, 7-12, 7-13, 7-14, 7-17, RGs 1.75 R2, 1.151RO 7-18, 7-21 For newly procured/major modified equipment, TVA will NUREG-0737, II.G.1 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO, 1.209 R0 For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment ifthere are approved vendor topical reports available to support the review.

7.4.1 .Description None 7.4.2 Analysis None Page 43 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP [ SRP Section Acceptance Criteria ssuesStatus Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision 7.5 Safety-Related Display 7.5 Information Systems 2007 10 CFR 50, App. A, GDC 1, 2, 4,13 See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation Important to Safety 19,24, .55a(a)(1), 50.55a(h) 1971.

RGs 1.47 R1, 1.53 R2, 1.75, 1.97 For newly procured/major modified equipment, TVA will R3, 1.105 R3, 1.118 R3, 1.151, use IEEE 603-1991, except for the TELEPERM XS system 1.152 R3, 1.168 R1, 1.169 RO, which will satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, TVA will use RG 1.97 R3 in lieu of R4.

1.173 RO, 1.180, 1.204, 1.209 BTP 7-10, 7-11, 7-12, 7-13, 7-14, 7- For existing (legacy) equipment, TVA will use the following:

17, 7-18, 7-21 RGs 1.75 R2, 1.151 R0.

NUREG-0737, I.D.3, ll.D.3, II.E.1.2, For newly procured/major modified equipment, TVA will II.F.1, II.F.2, II.F.3, II.G.1 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO, 1.209 RO.

For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there are approved vendor topical rennrts available to support the review.

7.5.1 Description None 7.5.2 Analysis None Page 44 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status 7.6 All Other 7.6 Interlock Systems 2007 10 CFR 50.55a(a)(1), 50.55a(h), See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation Systems Important to Safety App. A, GDC 1, 2, 4,10,13, 15, 16, 1971.

Required for Safety 19, 24, 25, 28, 33, 34, 35, 38, 41, For newly procured/major modified equipment, TVA will 44 use IEEE 603-1991, except for the TELEPERM XS system RGs 1.47 R1, 1.53 R2, 1.75, which will satisfy the requirements of IEEE 603-1998.

1.105 R3, 1.118 R3, 1.151, 1.152 R3, 1.168 R1, 1.169 R0, 1.170 RO, 1.171 RO, 1.172 RO, For existing (legacy) equipment, TVA will use the following:

1.173 RO, 1.180, 1.204, 1.209 RGs 1.75 R2, 1.151 RO BTP 7-1, 7-2, 7-5, 7-11, 7-12, 7- For newly procured/major modified equipment, TVA will 14, 7-17, 7-18, 7-21 use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 NUREG-0737, 1.D.3 RO, 1.209 RO For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there are approved vendor topical reports available to support the review.

7.6.1 Description None 7.6.2 Analysis None 7.7 Control Systems Not 7.7 Control Systems 2007 10 CFR 50.55a(a)(1), 50.55a(h), See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Required for Safety App. A, GDC 1, 10, 13, 15, 19, 24, 1971.

28, 29, 44, For newly procured/major modified equipment, TVA will RGs 1.75, 1.105 R3, 1.151, use IEEE 603-1991, except for the TELEPERM XS system 1.152 R3, 1.168 R1, 1.169 RO, which will satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 BTP 7-5, 7-11, 7-12, 7-14, 7-17, 7- For existing (legacy) equipment, TVA will use the following:

18, 7-19, 7-21 RGs 1.75 R2, 1.151 RO Page 45 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Ky Ise Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria AdtolIfrStatus NUREG-0737, I1.K.2.9 For newly procured/major modified equipment, TVA will use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 R0, 1.209 RO For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved., It may be useful for other equipment if there are approved vendor topical reports available to support the review.

7.7.1 Description None 7.7.2 Analysis None Page 46 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status 7.8 NSSS Interface 7.8 Diverse 2007 10 CFR 50.55a(a)(1), 50.55a(h), See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Instrumentation and 50.62, App. A, GDC 1, 13,19,24 1971.

Control Systems RGs 1.22 RO, 1.62 R1, 1.75, For newly procured/major modified equipment, TVA will 1.105 R3, 1.118 R3, 1.151, use IEEE 603-1991, except for the TELEPERM XS system 1.152 R3, 1.168 R1, 1.169 RO, which will satisfy the requirements of IEEE 603-1998.

1.170 RO, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 BTP 7-11, 7-12, 7-14, 7-17, 7-18, 7- For existing (legacy) equipment, TVA will use the following:

19, 7-21 RGs 1.75 R2, 1.151 RO For newly procured/major modified equipment, TVA will use the following: RGs 1.75 R3, 1.151 R1, 1.180 R1, 1.204 RO, 1.209 RO For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there.are approved vendor topical reports available to support the IrVIeW.

7.8 BOP Interface None None 7.9 Data Communication 2007 10 CFR 50. 50.55a(a)(1), See 7.0 See 7.0 For existing (legacy) equipment, TVA will use IEEE 279-Systems 50.55a(h), 50.62, App. A, GDC 1, 1971.

2, 4, 13, 19, 21,22, 23, 24, 29 For newly procured/major modified equipment, TVA will RGs 1.22 RO, 1.47 R1, 1.53 R2, use IEEE 603-1991, except for the TELEPERM XS system 1.75, 1.105 R3, 1.118 R3, which will satisfy the requirements of IEEE 603-1998.

1.152 R3, 1.168 Ri, 1.169 RO, For existing (legacy) equipment, TVA will use the following:

1.170 R0, 1.171 RO, 1.172 RO, 1.173 RO, 1.180, 1.204, 1.209 RG 1.75 R2 BTP 7-8, 7-11, 7-12, 7-14, 7-17,7- For newly procured/major modified equipment, TVA will 18, 7-19, 7-21 use the following: RGs 1.75 R3, 1.180 R1, 1.204 RO, 1.209 Page 47 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Isue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status RO For previously approved digital platforms (i.e., those with NRC SERs for vendor topical reports), the use of the applicable Regulatory Guides, Industry Standards, and other NRC guidance documents will be as specified in the NRC-approved topical reports. Specifically, this clarification now applies to the various TELEPERM XS topical reports and the Westinghouse ALS topical reports when they are approved. It may be useful for other equipment if there are approved vendor topical reports available to support the review.

None Appendix 7-A General 2007 Agenda, Station Site visits None Appendix 7-B Acronyms, 2007 Abbreviations, and Glossary None Branch Technical 1997 Positions (BTPs) - Index None BTP 7 Guidance on 2007 None NA Isolation of Low-Pressure Systems from the High-Pressure Reactor Coolant System None BTP 7 Guidance on 2007 None NA Requirements of Motor-Operated Valves in the Emergency Core Cooling System Accumulator Lines None BTP 7 Guidance on 2007 None NA Protection System Trip Point Changes for Operation with Reactor Page 48 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision S! Acceptance Criteria iSauKey Issue(s) Additional Information Coolant Pumps Out of Service None BTP 7 Guidance on 2007 None NA Design Criteria for Auxiliary Feedwater Systems None BTP 7 Guidance on 2007 None NA Spurious Withdrawals of Single Control Rods in Pressurized Water Reactors None BTP 7 Guidance on 2007 None NA Design of Instrumentation and Controls Provided to Accomplish Changeover from Injection to Recirculation Mode None BTP 7 Guidance for 2007 None NA Application of Regulatory Guide 1.22 None BTP 7 Guidance on 2007 None NA Requirements for Reactor Protection System Anticipatory Trips None BTP 7 Guidance on 2007 None NA TVA will use RG 1.97 R3 in lieu of R4.

Application of Regulatory Guide 1.97 None BTP 7 Guidance on 2007 None NA Application and Qualification of Isolation Devices Page 49 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria K Status None BTP 7 Guidance on 2007 None NA IEB 79-21, Temperature Effects on Level Measurements Establishing and Maintaining Instrument Setpoints None BTP 7 Guidance on 2007 None NA Cross-Calibration of Protection System Resistance Temperature Detectors None BTP 7 Guidance on 2007 None NA Software Reviews for Digital Computer-Based Instrumentation and Control Systems None BTP 7 Guidance on None NA NA to BLN - Part 52 the Level of Detail Required for Design Certification Applications Under 10 CFR Part 52 None BTP 7 Guidance on 2007 None NA Self-Test and Surveillance Test Provisions None BTP 7 Guidance on 2007 None NA the Use of Programmable Logic Controllers in Digital Computer-Based Instrumentation and.

Control Systems Page 50 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s) Additional Information None BTP 7 Guidance for 2012 None NA Evaluation of Diversity and Defense-in-Depth in Digital Computer-Based Instrumentation and Control Systems None BTP 7 Guidance on 2007 None NA Digital Computer Real-Time Performance Page 51 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information Revision Acceptance Criteria Status RG 1.70 (FSAR) Section Section Chapter 8 - Electric Power

8. Electric Power None 8.1 Introduction 8.1 Electric Power- 2012 Introduction 8.2 Offsite Power System 8.2 2010 10 CFR 50 App A, GDCs 2, 4, 5, None NA For newly procured/major modified equipment, TVA will 17, 18, 33, 34, 35, 38, 41, & 44, use RG 1.204 RO.

50.63, 50.65(a)(4)

RGs 1.32 R3, 1.155 RO, 1.160 R3, 1.204 NUREG-0737, I.D.3 8.2.1 Description None 8.2.2 Analysis None 8.2.3 NSSS Interface None 8.2.3 BOP Interface None 8.3 Onsite Power Systems None 8.3.1 A. C. Power Systems 8.3.1 AC Power Systems 2012 10 CFR 50, App A, GDCs 2, 4, 5, Cables: TVA will review Regarding RG 1.81, BLN AC power systems will be shared (Onsite) 17, 18, 33, 34, 35, 38, 41, 44 & 50, , Sidewall its existing systems.

50.55a(h), 50.63, 50.65(a)(4) Bearing Position Papers For existing (legacy) equipment, TVA will use IEEE 279-RGs 1.6 RO, 1.9 R4, 1.32 R3, Pressure and and the NRC 1971.

1.47 R1, 1.53 R2, 1.63, 1.75, Jamming SER dated For newly procured/major modified equipment, TVA will 1.81 R1, 1.106 R1, 1.118 R3, a Bend Radius 10/28/91 on use IEEE 603-1991.

1.153, 1.155 R0, 1.160 R3, 1.204 cables.

B. 853 Pullby TVA will use RG 1.106 R1 in lieu of R2.

BTP 8-5 NUREG/CR-0660 For existing (legacy) equipment, TVA will use the following:

NUREG-0737, I.D.3, II.E.3.1, II.G.1 RGs 1.63 R2, 1.75 R2 For newly procured/major modified equipment, TVA will use the following: RGs 1.63 R3, 1.75 R3, 1.153 R1, 1.204 RO Page 52 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Iss() KeyIssue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Criteria KAcceptance Status For newly procured equipment, TVA will use recently issued RG 1.213 (which is not referenced in SRP Section 8.3.1).

The BLN Cable Monitoring Program will use the guidance contained in recently issued RG 1.218 RO.

8.3.2 D. C. Power Systems 8.3.2 DC Power Systems 2010 10 CFR 50 App A, GDCs 2, 4, 5, None NA For existing (legacy) equipment, TVA will use IEEE 279-(Onsite) 17, 18, 33, 34, 35, 38, 41,44, 50, 1971.

50.55a(h), 50.63, 50.65(a)(4) For newly procured/major modified equipment, TVA will RGs 1.6 RO, 1.32 R3, 1.47 R1, use IEEE 603-1991.

1.53 R2, 1.63, 1.75, 1.106 R1, 1.118 R3, 1.128, 1.129, 1.153, TVA will use RG 1.106 R1 in lieu of R2.

1.155 RO, 1.160 R3, 1.204 NUREG-0737, BTP 8-5 1.D.3 RG 1.81, which is referenced in this SRP Acceptance Criteria section, is not applicable to BLN as the DC Power Systems are unitized.

For existing (legacy) equipment, TVA will use the following:

RGs 1.63 R2, 1.75 R2, 1.128 R!, 1.129 R!.

For newly procured/major modified equipment, TVA will use the following: RGs 1.63 R3, 1.75 R3, 1.128 R2, 1.129 R2, 1.153 R1, 1.204 RO For newly procured equipment, TVA will use recently issued RGs 1.210 and 1.212 (which are not referenced in SRP Section 8.3.2).

The BLN Cable Monitoring Program will use the guidance contained in recently issued RG 1.218 RO.

GL 80-18, Crystal River 3 Reactor Trip From Approximately 100% Full Power Page 53 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section FKey Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance CriteriaK Status 8.3.3 Fire Protection for I None Cable systems None 8.4 Station Blackout 2010 10 CFR 50, App A, GDCs 17 & 18, Station Blackout TVA will address TVA is considering using the alternate AC option from 10 50.63, .65(a)(4) Station Blackout CFR 50.63; however, a final decision will not be made until.

RGs 1.9 R4, 1.155 RO, 1.160 R3 in response to the full scope of the Fukushima action items are USI A-44 understood and harmonized.

None Appendix 8-A General 2007 Agenda, Station Site Visits (formerly Appendix B)

None 8-A Branch Technical 1996 Positions (PSB) (Draft)

None 8-B General Agenda, 1996 Station Site Visits (Draft)

None BTP 8 Requirements 2007 None None NA on Motor-Operated Valves in the ECCS Accumulator Lines None BTP 8 Use of Diesel- 2007 None None NA Generator Sets for IPeaking None BTP 8 Stability of 2007 None None NA Offsite Power Systems None BTP 8 Application of 2007 None None NA the Single Failure Criterion to Manually Controlled Electrically Operated Valves Page 54 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status None BTP 8 Supplemental 2007 None None NA Guidance for Bypass and Inoperable Status Indication for Engineered Safety Features Systems None BTP 8 Adequacy of 2007 None None NA Station Electric Distribution System Voltages None BTP 8 Criteria for 2007 None None NA Alarms and Indications Associated with Diesel-Generator Unit Bypassed and Inoperable Status None BTP 8 Onsite 2012 None None NA (Emergency Diesel Generators) and Offsite Power Sources Allowed I Outage Time Extensions Page 55 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

RG 1,70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status Chapter 9 - Auxiliary Systems

9. Auxiliary Systems None 9.1 Fuel Storage and None Handling 9.1.1 New Fuel Storage 9.1.1 Criticality Safety of 2007 10 CFR 50 App. A, GDC 62, 50.68 None NA Existing fuel racks require evaluation for conformance to Fresh and Spent Fuel 10 CFR 70.24 ANSI/ANS 57.2 and 57.3.

Storage Handling ANSI/ANS 57.1, 57.2, 57.3 9.1.2 Spent Fuel Storage 9.1.2 New and Spent Fuel 2007 10 CFR 50 App. A, GDCs 2,4, 5, None NA TVA will use RG 1.115 RI in lieu of R2.

Storage 61, 63, 50.68 10 CFR 70.24, Existing fuel racks require evaluation for conformance to 10 CFR 20.1101(b) ANSI/ANS 57.2 and 57.3.

RGs 1.13 R2, 1.29 R4, 1.115 R1, 1.117 R1, 8.8 R3 ANS 57.2, 57.3 9.1.3 Spent Fuel Pool 9.1.3 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Cooling and Cleanup 61,63 For newly procured/major modified equipment WVA will use System 10 CFR 20.1101(b) RG 1.52 R4.

RGs 1.13 R2, 1.26 R4, 1.29 R4, 1.52 9.1.4 Fuel Handling System 9.1.4 Light Load Handling 2007 10 CFR 50 App. A, GDCs 2, 5, 61, None NA System (Related to 62 Refueling) RG 1.29 R4 ANSI/ANS 57.1-1992 Page 56 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 9.1.5 Overhead Heavy 2007 10 CFR 50 App. A, GDCs 1,2, 4, 5 None NA Implementation of ASME NOG-1 ia an acceptable method Load Handling Systems 10 CFR 100, Subpart B of complying with NUREG-0554.

RGs 1.13 R2, 1.29 R4 TVA will use the guidance in NUREG-0612, Control of NUREG 0554 Heavy Loads.

ANSI N14.6 ASME B30.9 9.2 Water Systems None 9.2.1 Station Service Water 9.2.1 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA System 44, 45, 46 RG 1.29 R4 GL 89-13, GL 96-06 9.2.2 Cooling System for 9.2.2 Reactor Auxiliary 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For newly procured/major modified equipment TVA will use Reactor Auxiliaries Cooling Water System 44,45,46 RG 1.153 R1.

RGs 1.29 R4, 1.153, 1.155 R0 BTP ASB 3-1, 3-3 GL 96-06 9.2.3 Demineralized Water 9.2.3 Section 9.2.3 Withdrawn NA NA Makeup System 9.2.4 Potable and Sanitary 9.2.4 2007 10 CFR 50 App. A, GDC 60 None NA The Potable and Sanitary Water Systems serve no safety Water Systems related functions 9.2.5 Ultimate Heat Sink 9.2.5 2007 10 CFR 50 App. A, GDCs 2,5,44, None NA 45,46 RGs 1.27 R2 (For Comment), 1.72 R2 Page 57 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 9.2.6 Condensate Storage 9.2.6 2007 10 CFR 50 App. A, GDCs 2, 5,44, None NA The Condensate Storage and Transfer System serves no Facilities 45, 46, 60, 50.63 safety related function RGs 1.29 R4, 1.59 R2, 1.76 R1, 1.102 R1, 1.117 R1, 1.143 R2, 1.155 RO 9.2.7 BOP Interface None 9.3 Process Auxiliaries None 9.3.1 Compressed Air 9.3.1 Compressed Air 2007 10 CFR 50 App. A, GDCs 1, 2, 5, None NA Systems System 50.63 RGs 1.29 R4, 1.155 RO ANSI/ISA $7.3-R1981 9.3.2 Process Sampling 9.3.2 Process and Post- 2007 10 CFR 50 App, A, GDCs 1, 2,13, None NA TVA will use RG 1.97 R3 in lieu of R4.

System accident Sampling 14, 26, 41,60, 63,64 systems 10 CFR 20.1101 (b) TMI Action Item - II.B.3, Post-accident sampling.

RGs 1.21 R2, 1.26 R4, 1.29 R4, 1.97 R3, 8.8 R3 NUREG-0737, II1.D.1.1 ANSI/HPS N13.1-1999 9,3.3 Equipment and Floor 9.3.3 2007 10 CFR 50 App. A, GDCs 2, 4, 60 None NA Drainage System 93.4 Chemical and Volume 9.3.4 Chemical and 2007 10 CFR 50 App. A, GDCs 1, 2, 5, None NA Control System Volume Control System 14, 29, 33, 35, 60, 61, 50.55(a),

(PWR) (Including Boron 50.63(a)(2)

Recovery System) RGs 1.26 R4, 1.29 R4, 1.155 RO NUREG-0737, IlI.D.1.1 IEB 80-05 9.3.5 Standby Liquid 9.3.5 Standby Liquid NA - BWRs only Control System Control System (BWR)

Page 58 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRPcSRP Section ]Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Rev s on Acceptance Criteria Status 9.4 Air Conditioning, None Heating, Cooling, and Ventilation Systems 9.4.1 Control Room Area 9.4.1 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For existing (legacy) equipment TVA will use RGs 1.52 R1 Ventilation System 19, 60; 50.63 and 1.140 Ri.

10 CFR Part 20 For newly procured/major modified equipment TVA will use RGs 1.29 R4, 1.52, 1.78 R1, RGs 1.52 R3 and 1.140 R2.

1.140, 1.155 RO 9.4.2 Spent Fuel Pool Area 9.4.2 2007 10 CFR 50 App: A, GDCs 2, 5, 60, None NA For existing (legacy) equipment TVA will use RGs 1.52 R1 Ventilation System 61 and 1.140 RI.

10 CFR Part 20 For newly procured/major modified equipment TVA will use RGs 1.13 R2, 1.25 RO, 1.29 R4, RGs 1.52 R3 and 1.140 R2.

1.52, 1.140 9.4.3 Auxiliary and 9.4.3 2007 10 CFR 50 App. A, GDCs 2, 5, 60 None NA For existing (legacy) equipment WVA will use RGs 1.52 R1 Radwaste Area Ventilation 10 CFR Part 20 and 1.140 RI.

System RGs 1.29 R4, 1.52, 1.140 For newly procured/major modified equipment WVA will use RGs 1.52 R3 and 1.140 R2.

9.4.4 Turbine Building Area 9.4.4 Turbine Area 2007 10 CFR 50 App. A, GDCs 2, 5, 60 None NA For existing (legacy) equipment TVA will use RGs 1.52 R1 Ventilation System Ventilation System 10 CFR Part 20 and 1.140 R1.

RGs 1.29 R4, 1.52, 1.140 For newly procured/major modified equipment TVA will use RGs 1.52 R3 and 1.140 R2.

The Turbine Building Area Ventilation System serves no safety function.

9.4.5 Engineered-Safety- 9.4.5 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA For existing (legacy) equipment WVA will use RGs 1.52 R1 Feature Ventilation System 17, 60; 50.63 and 1.140 RI.

10 CFR Part 20 For newly procured/major modified equipment TVA will use RGs 1.29 R4, 1.52,1.140,1.155 RGs 1.52 R3 and 1.140 R2.

RO TMI Action Item - II.E.4.1, Dedicated Hydrogen NUREG-CR10660 Penetrations 9.4.6 BOP Interface None Page 59 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section s Key Issue(s) A Se nAcceptance Criteria I Status RG 1.70 (FSAR) Section Section Revision Key Issue(s) Status 9.5 Other Auxiliary Systems None 9.5.1 Fire Protection None System None 9.5.1.1 Fire Protection NA This section is not applicable since TVA will implement a Program risk-informed, performance-based fire protection program consistent with the methodology of the NFPA 805 standard.

See SRP Section 9.5.1.2.

None 9.5.1.2 Risk-Informed (RI) 2009 10 CFR 50 App. A, GDC 3, BLN Fire TVA will update Although 10 CFR 50.48(c)(3)(i) does not specifically apply Performance-Based (PB) 50.48(a), .48(c), .109 Protection the BLN fire to BLN, TVA plans to implement a FPP at BLN that Fire Protection Program 10 CFR Part 20 Licensing Basis protection complies with NFPA 805 as an alternative to the (FPP) RGs 1.174 R2, 1.189 R2, licensing basis requirements of 10 CFR 50.48(b).

1.200 R2, 1.205 R1 for this issue NUREGs-1600, -1824, 1852, CR- (TAC No. 79283) TVA plans to submit its position on implementation of a 6850 since TVA will risk-informed, performance-based FPP consistent with the NRC Management Directive 8.4 implement a risk- methodology of the NFPA 805 standard as the BLN NFPA 805 (2001 Version) informed, licensing basis.

performance-based FPP.

9.5.2 Communication 9.5.2 Communications 2007 10 CFR 50 App. A, GDCs 1, 2, 3, None NA Systems Systems 4, 19, .47(a)(8), .55a, App. E 10 CFR 73.20(a), .45(e)(2)(iii),

.45(g)(4)(i), .46(e)(5), .46(f), .55(e),

(f)

NUREG-0737, IIl.A.1.2 9.5.3 Lighting Systems 9.5.3 2007 NUREG-0700 None NA 9.5.4 Diesel Generator Fuel 9.5.4 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Oil Storage and Transfer Engine Fuel Oil Storage 17 the DG support systems.

System and Transfer System RGs 1.29 R4, 1.137 R1 NUREG/CR-0660 ASME Section XI, ANSI/ANS 59.51 Page 60 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) KeyStatus Ke Issue(s) sus)AdtoaInrmin Additional Information Sco vso Acceptance Cie RG 1.70 (FSAR) Section Section Revis on Criteria 9.5.5 Diesel Generator 9.5.5 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Cooling Water System Engine Cooling Water 17, 44, 45, 46 the DG support systems.

System RG 1.29 R4 NUREG/CR-0660 9.5.6 Diesel Generator 9.5.6 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Starting System Engine Starting System 17 the DG support systems.

RG 1.29 R4 NUREG/CR-0660 9.5.7 Diesel Generator 9.5.7 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Lubrication System Engine Lubrication System 17 the DG support systems.

RG 1.29 R4 ANSI/ANS 59.52 NUREG/CR-0660 9.5.8 Diesel Generator 9.5.8 Emergency Diesel 2007 10 CFR 50 App. A, GDCs 2, 4, 5, None NA TVA will use Code of Record and applicable code cases for Combustion Air Intake and Engine Combustion Air 17 the DG support systems.

Exhaust System Intake and Exhaust RG 1.29 R4 System NUREG/CR-0660 Page 61 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 10 - Steam and Power Conversion System

10. Steam and Power None Conversion System 10.1 Summary Description None 10.2 Turbine Generator 10.2 2007 10 CFR 50, App. A, GDC 4 None NA 10.2.1 Design Bases None 10.2.2 Description None 10.2.3 Turbine Disk 10.2.3 Turbine Rotor 2007 10 CFR 50, App. A, GDC 4 None NA Integrity Integrity 10.2.4 Evaluation None 10.3 Main Steam Supply 10.3 2007 10 CFR 50, App. A, GDCs 2,4, 5, None NA TVA will use RG 1.115 R1 in lieu of R2.

System & 34, 50.63; RGs 1.29 R4, 1.115 R1, 1.117 R1, 1.155 R0 10.3.1 Design Bases None 10.3. 2 Descripiion None 10.3.3 Evaluation None 10.3.4 Inspection and None Testing Requirements 10.3.5 Water Chemistry None Page 62 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Isse(s) Key Issue(s) Additional Information Section Revision Acceptance Criteria Status 10.3.6 Steam and 10.3.6 2007 10 CFR 50,55a, App. A, GDCs 1, None NA For existing (legacy) equipment, TVA will use the following:

Feedwater System & 35, App. B; RGs 1.37 RO, 1.50 RO, 1.71 RO Materials RGs 1.37, 1.50, 1.71, 1.84 For newly procured/major modified equipment, TVA will use the following: RGs 1.37 R1, 1.50 R1, 1.71 Ri.

Revision of RG 1.84 will be consistent with requests to use Code Cases.

10.4 Other Features of None Steam and Power Conversion System 10.4.1 Main Condensers 10.4.1 2007 10 CFR 50, App. A, GDC 60 None NA 10.4.2 Main Condenser 10.4.2 2007 10 CFR 50, App. A, GDC 60 None NA Evacuation System 10.4.3 Turbine Gland 10.4.3 2007 10 CFR 50, App. A, GDCs 60 None NA Sealing System 10.4.4 Turbine Bypass 10.4.4 2007 10 CFR 50, App. A, GDCs 4 & 34 None NA System 10.4.5 Circulating Water 10.4.5 2007 10 CFR 50, App. A, GDC 4 None NA System 10.4.6 Coodensaie i10.4.6 2007 10 CFR 50 App. A, GDC 14; None NA Cleanup System 10.4.7 Condensate and 10.4.7 Condensate and 2007 10 CFR 50, App. A GDCs 2, 4, 5, None NA Feedwater Systems Feedwater System 44, 45, 46; RG 1.29 R4; BTP 10-2 NUREG-0927 10.4.8 Steam Generator 10.4.8 Steam Generator 2007 10 CFR 50, App. A GDCs 1, 2,13, None NA Blowdown System Blowdown System (PWR) & 14; RG 1.143 R2 Page 63 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan RGNUREG 0800 (SRP) SRP SRP Section Key Issue(s) 10.4.9 Auxiliary Feedwater 10.4.9 Auxiliary Feedwater 2007 10 CFR 50, App. A, GDCs 2,4,5, None NA BLN is a Class 2 plant relative to implementing the System System (PWR) 19, 34, 44, 45, 46, 50.34(f), 50.62, requirements of BTP 5-4.

50.63 BTPs 3-3, 5-4, 10-1 RGs 1.29 R4, 1.102 R1, 1.117 R1, 1.155 RO NUREGs 0611, 0635 &

0737,11.E.1.1 None BTP 10-1 Design NRC staff established design None NA Guidelines for Auxiliary guidelines for the auxiliary Feedwater System Pump feedwater system Drive and Power Supply Diversity for Pressurized Water Reactor Plants None BTP 10-2 Design NRC staff established design None NA Guidelines for Avoiding guidelines for avoiding water Water Hammers in Steam hammer in steam generators.

Generators Page 64 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Chapter 11 - Radioactive Waste Management

11. Radioactive Waste None None NA Management 11.1 Source Terms 11.1 2007 10 CFR 20.1301, .1301 (e), App B, None NA For existing (legacy) equipment TVA will use RG 1.140 RI.

10 CFR 50.34, .34a, App. A, GDC For newly procured/major modified equipment TVA will use 60 and App. I RG 1.140 R2.

RGs 1.110 RO, 1.112 R1, 1.140 NUREG-0017 ANSI/ANS 18.1-1999 11.2 Liquid Waste 11.2 Liquid Waste 2010 10 CFR 20 Sections 1301, None NA Management Systems Management System 1301(e), 1302 and 1406; 10 CFR 50.34a, App. A, GDCs 60, 61, App. I; 40 CFR 190 RGs 1.109 R1, 1.110 RO, 1.112 R1, 1.113 R1, 1.143 R2 BTP 11-6 NUREG-0017 11.2.1 Design Bases None 11.2.2 System Description None 11.2.3 Radioactive None Releases 11.2.4 BOP Interface None Page 65 of 91

Enclosure I TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan RG1.70 (FSAR) Section 11.3 Gaseous Waste f _

11.3 NUREG 0800 (SRP)

Section SRP Revision 2007 SRP Section Acceptance Criteria 10 CFR 20.1301,.1301 (e), 1302, Key Issue(s)

None NA KeyIssue Status Additional Information BLN will use plant specific x/Q values for gaseous tank Management Systems 1406, App. B; failure analysis in lieu of the guidance contained in RG 10 CFR 50.34a, App. A, GDCs 3, 1.24.

60, 61, App. I; For existing (legacy) equipment TVA will use RG 1.140 R1.

40 CFR 190 RGs 1.109 R1, 1.110 RO, For newly procured/major modified equipment TVA will use 1.111 R1, 1.112 R1, 1.140,1.143 RG 1.140 R2.

R2 BTP 11-5 NUREG-0017 11.3.1 Design Bases None 11.3.2 System Description None 11.3.3 Radioactive None Releases 11.3.4 BOP Interface None 11.4 Solid Waste 11.4 2007 10 CFR 20.1302, 1301(e), 1406, None NA Management System 2006, 2007, 2108, App B, App G 10 CFR 50. 34a, App A, GDCs 60, 61, 63, App I 40 CFR 190, 10 CFR 61, 61.55 & .56, 10 CFR 71 49 CFR 171-180 RGs 1.110 RO, 1.112 R1, 1.143 R2 NUREG -0017 BTP 11-3 11.4.1 Design Bases None 11.4.2 System Description None Page 66 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 11.5 Process and Effluent 11.5 Process and Effluent 2010 10 CFR 20.1302, 1301,1301 (e), None NA TVA will use RG 1.97 R3 in lieu of R4.

Radiological Monitoring and Radiological Monitoring 1406 Sampling Systems Instrumentation and 10 CFR 50.34a, .34(f), .36a, App Sampling Systems A, GDCs 60, 63 & 64, & App I RGs 1.21 R2, 1.97 R3, 4.15 R2, 1.33 R2, App A BTP 7-10 11.5.1 Design Bases None 11.5.2 System Description None 11.5.3 Effluent Monitoring None and Sampling 11.5.4 Process Monitoring None and Sampling None BTP 11-3 Design Requirements noted in Section None NA Guidance for Solid 11.4 Radioactive Waste Management Systems Installed in Light-Water-Cooled Nuclear Power Re-actor PlantsI None BTP 11-5 Postulated Requirements noted in Section None NA BLN will use plant specific x/Q values for gaseous tank Radioactive Releases Due 11.3 failure analysis in lieu of the guidance contained in RG to a Waste Gas System 1.24.

Leak or Failure None BTP 11-6 Postulated Requirements noted in Section None NA Radioactive Releases Due 11.2 to Liquid-containing Tank Failures Page 67 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key I() Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section AcceptanceIsue Criteriaa Inormtio Chapter 12 - Radiation Protection

12. Radiation Protection None 12.1 Ensuring that 12.1 Assuring that 2007 10 CFR 19.12,. None NA Occupational Radiation Occupational Radiation 10 CFR 20.1101, 1101(b), & 1003 Exposures Are As Low As Exposures Are As Low As RGs 1.33 R2, 1.8 R3, 8.8 R3, Is Reasonably Achievable Is Reasonably Achievable 8.10 R1, 8.27 RO NUREG 1736 12.1.1 Policy None Considerations 12.1.2 Design None Considerations 12.1.3 Operational None Considerations 12.2 Radiation Sources 12.2 2007 10 CFR 20.1201, .1202, .1203, None NA

.1204, 1206, .1207, .1301, &

-.1801, App B 10 CFR 50, App A, GDCs 19 &

61.

RGs 1.4 R2, 1.7 R3, 1.112 R1, 1.183 RO NUREG 0737, lI.B.2 12.2.1 Contained Sources None 12.2.2 Airborne Radioactive None Material Sources Page 68 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Ke Kessue su) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 12.3 Radiation Protection 12.3 - 12.4 Radiation 2011 10 CFR 20 For existing (legacy) equipment TVA will use RG 1.52 R1.

Design Features Protection Design 10 CFR 50.68, App A, GDCs 19, For newly procured/major modified equipment TVA will use 12.4 Dose Assessment Features 61,63 RG 1.52 R4.

RGs 1.4 R2, 1.7 R3, 1.52, TVA will use RG 1.69 RO in lieu of R1.

1.69 RO, 1.97 R3, 1.183 RO, TVA will use RG 1.97 R3 in lieu of R4.

8.2 R1, 8.8 R3, 8.10 Ri, 8.19 Ri, 8.25 R1, 8.38 R1 NUREG 0737, ll.B.2, IF5.1, NUREG 1430, NUREG/CR-3587 ANSI/ANS-HPSSC-6.8.1-1981, ANSI N13.1-1999, ANSI/ANS-6.4-1997(R004) 12.3.1 Facility Design None Features 12.3.2 Shielding None 12.3.3 Ventilation None 12.3.4 Area Radiation and None Airborne Radioactivity Monitoring Instrumentation See 12.4 above See 12.3 - 12.4 above Page 69 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 12.5 Health Physics 12.5 Operational Radiation 2010 10 CFR 19.12, .13 None NA TVA will use RG 1.97 R3 in lieu of R4.

Program Protection Program 10 CFR 20 10 CFR 50.120, App A, GDC 64, App B 10 CFR 71.5 & Subparts H & G.

RGs 1.8 R3, 1.33 R2, 1.97 R3, 8.2 R1, 8.4 R1, 8.7 R2, 8.8 R3, 8.9 R1, 8.10 R1, 8.13 R3, 8.15 R1, 8.20 R1, 8.25 R1, 8.26 RO, 8.27 RO, 8.28 RO, 8.29 R1, 8.32 RO, 8.34 RO, 8.35 R1, 8.36 RO, 8.38 R1 NUREGs 0041, 0731, 1736, 0737, lI.B.3 & II1.D.3.3, NUREG/CR-3587 ANSI/ANS 3.1-1978, ANSI N13.6-1999, N42.17A-2003, N42.20-2003, N323A-1 997, ANSI/HPS N13.11-2001, N13.14-1994, N13.30-1996, N13.42-1997

________________ _______IEEE 309-1991 ______ ______________________

None 12.5.1 Organization 12.5.2 Equipment, None Instrumentation, and Facilities 12.5.3 Procedures None Page 70 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan RG 1,70 (FSAR) Section NUREG 0800 (SRP)

Section_____ SRP Revision___ SRP Section Key Issue(s)

Key_____Issue_____ Key Issue(s)

_s)____Additional_____________nformation_________

Additional Information Section Revision Acceptance Criteria Status Chapter - 13 Conduct of Operations

13. Conduct of Operations None 13.1 Organizational None structure of Applicant 13.1.1 Management and 13.1.1 2007 10 CFR 50.40(b) None NA Technical Support RG 1.8 R3 Organization NUREG-0694, I.B.1.2 13.1.2 Operating 13.1.2 - 13.1.3 2007 10 CFR 50.40(b), .54(j, k, I&m) None NA Organization RGs 1.8 R3, 1.33 R2, 1.114 R3 NUREG-0694, I.B.1.2 and I.C.3 NUREG-0737, I.A.1.1 and I.A.1.3 NUREG-1791 BTP SPLB 9.5-1, ANSI N18.7/ANS-3.2 13.1.3 Qualifications of None Nuclear Plant Personnel 13.2 Training None 13.2.1 Plant Staff Training 13.2.1 Reactor Operator 2007 10 CFR 50.54, i - m None NA The guidelines contained in NEI-06-13A R2 will be used in Program Requalification Program; 10 CFR 55.4,31, .41, .43, .45, .46, lieu of RG 1.8 R3 for the qualifications required for SRO Reactor Operator Training .59, and RO candidates.

RGs 1.8 R3, 1.149 R4 TMI Action Item - I.A.2.3, Administration of training NUREGs-0711, 1021, 1220 programs.

NEI-06-13A, R2 TMI Action Item - I.A.3.1, Revise scope & criteria for licensing exams.

TMI Action Item - II.B.4, Training For Mitigating Core Damage TMI Action Item - I1.K.2.2, Procedures to Control AFW Indication Page 71 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Ky Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status 13.2.2 Replacement and 13.2.2, Non-Licensed 2007 10 CFR 19.12 None NA Retraining Plant Staff Training 10 CFR 26.21, .22 10 CFR 50.34(b), .40(b), .120, App.

E,Section II.F, and Section IV.F 10 CFR 55.4 RGs 1.8 R3, 1.149 R4 NUREGs-0711, 1220 BTP SPLB 9.5-1 13.2.3 Applicable NRC None Documents 13.3 Emergency Planning 13.3 2007 10 CFR 50.33, .34, 50.47, App. E, None NA TVA will use RG 1.97 R3 in lieu of R4.

.72(a)(3), .72(a)(4), .72(c)(3) TMI Action Item - III.A.1.1, Emergency Preparedness, 10 CFR 73.71 (a) Short Term 10 CFR 100.1, .3, .10(d), .20,

.21 (g) 44 CFR Parts 350, 351, 352 RGs 1.23 R1, 1.97 R3, 1.101 R5, 5.62 R1 NUREG-0737, I.D.2, lI.B.3, II.F.1, and II1.A.1.2 ICMs B.5.c, B.5.d, B.5.e of Commission Orders of 2/25/02 NUREG-0396, 0654/FEMA-REP-1, Ri,0696, 0718, 0737, 0814, 1394, 1022 NEI 99-01 13.3.1 Preliminary Planning None 13.3.2 Emergency Plan None 13.3.3 BOP Interface None Page 72 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s)

RG 1.70 (FSAR) Section Section Revision AcceptanceKey Issue(s) Additional Information 13.4 Review and Audit 13.4 Operational None None NA Requirements are addressed in other SRP sections.

Programs 13.4.1 Onsite Review None 13.4.2 Independent Review None 13.4.3 Audit Program None 13.5 Plant Procedures None 13.5.1 Administrative 13.5.1 NA None NA Superseded by 13.5.1.1 Procedures None 13.5.1.1 Administrative 2011 10 CFR 26, 50.40(a), 50.40(b), & None NA TMI Action Item - I.C.7, NSSS vendor rev of proc.

Procedures - General 50.54(l) 10 CFR 73.58 RGs 1.33 R2, 1.114 R3 NUREGs 0694, I.A.1.2, I.C.2, I.C.3, I.C.4, 0711, 0737, I.C.5 &

I.C.6, 0899 ANSI/ANS 3.2-1982, Section 5.2, ANSI B30.2-1976, Chapters 2 & 3 None 13.5.1.2 Administrative None None NA Requirements are addressed in SRP 14.2.

Procedures -initial Test Program 13.5.2 Operating and None Maintenance Procedures Page 73 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Isse(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 13.5.2.1 Operating and 2007 10 CFR 50.34(b)(6)(iv) & (v), App. None NA GL 81-21, Natural Circulation Cooldown Emergency Operating B, Criteria V & VI, Procedures RG 1.33 R2 NUREGs-071 1, Chapter 9, Element 8, NUREG-0899, NUREG- 0737, I.C.1, Supplement 1 to NUREG-0737,l.C.1, Supplement I to NUREG-1358, ANSI/ANS 3.2-1982, Section 5.3 None 13.5.2.2 Maintenance and None None NA Requirements are addressed in other SRP sections.

Other Operating Procedures 13.6 Industrial Security 13.6 Physical Security None None NA Requirements are addressed in other SRP sections.

13.6,1 Preliminary Planning 13.6.1 Physical Security- 2010 10 CFR 26, TVA will consider Preparing The Physical Security section is one of three security Combined License and 10 CFR 50.34(c) & (d), .54(p), the satisfaction of position paper on elements that must be addressed by TVA for BLN. The first Operating Reactors .54(x), .54(y) the requirements security which part relates to aircraft hazards (SRP 3.5.1.6) and will 10 CFR 73, Apps. B & C, .1, .2, specified in this will include address the requirements of 10 CFR 50.54(hh) related to

.21, .22, .23, .54, .55, .56, .57, 58, section as part of physical security, threat notification and maintenance of communications

.70 an overall regarding a threat. The second part involves physical RG 5.75 RO programmatic security and requirements for it are identified in this section.

NEI-03-12, scope to address The third is Cyber Security and is addressed in Section the various 13.6.6.

aspects of Security included in the 2007 SRP.

13.6.2 Security Plan 13.6.2 Physical Security - NA None NA Design Certification 13.6.3 NSSS Interface 13.6.3 Physical Security- NA None NA Page 74 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Early Site Permit 13.6.3 BOP Interface None None 13.6.6 Cyber Security Plan 2010 10 CFR 73.54, .55, .58, App G to Cyber Security Preparing 10 CFR 73 summary RG 5.71 RO discussion on NEI- 08-09 Cyber Security.

Page 75 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan RG 1.70 (FSAR) Section NUREG 0800 (SRP)

{KeyIsus)AdtoaInrmin SSRP Section___Revision Revision Section ceptance Criteria ASSection K s Key Issue(s)

Status Additional Information Chapter 14 - Initial Test Program

14. Initial Test Program None 14.1 Specific Information to None NA NA NA be Included in Preliminary Safety Analysis Reports 14.1.1 Scope of Test None Program 14.1.2 Plant Design None Features that are Special, Unique, or First of a Kind 14.1.3 Regulatory Guides None 14.1.4 Utilization of Plant None Operating and Testing Experiences at Other Reactor Facilities 14.1.5 Test Program None Schedule 14.1.6 Trial Use of Plant None Operating and Emergency Procedures 14.1.7 Augmenting None Applicant's Staff During Test Program 14.1.8 NSSS Interface None 14.1.8 BOP Interface None Page .76 of 91

Enclosure I TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status 14.2 Specific Information to 14.2 Initial Plant Test 2007 10 CFR 30.53(c); None NA BLN intends to use the preoperational testing guidance be Included in Final Safety Program - Design 10 CFR 50.34 (b) (6)(iii); App. B, contained in the following RGs: RG 1.30 RO, 1.41 RO, Analysis Reports Certification and New Section XI; App. J,Section III.A.4 1.68.1 R2, 1.68.2 R2, 1.68.3 R1, 1.79 R1 (with the License Applicants RG 1.68 R3 exception of Regulatory Position C.1.b(2) relative to NUREG-0737, Item I.G.1 recirculation testing at cold conditions).

14.2.1 Summary of Test 14.2.1 Generic Guidelines NA NA NA Program and Objectives for Extended Power Up rate Testing Programs 14.2.2 Organization and None Staffing 14.2.3 Test Procedures None 14.2.4 Conduct of Test None Program 14.2.5 Review, Evaluation, None and Approval of Test Results 14.2.6 Test Records None 14.2.7 Conformance of Test None Programs w.ith Regulatory Guides 14.2.8 Utilization of Reactor None Operating and Testing Experiences in Development of Test Program 14.2.9 Trial Use of Plant None Operating and Emergency Procedures Page 77 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

Key Issue(s) StatusAdditional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria 14.2.10 Initial Fuel Loading None and Initial Criticality 14.2.11 Test Program None Schedule 14.2.12 Individual Test None Descriptions None 14.3 Standard Plant DELETED DELETED DELETED DELETED Designs, Initial Test Program - Final Design Approval (FDA)

[DELETED]

None 14.3 Inspections, Tests, NA NA NA See 14.2 Analyses, and Acceptance Criteria None 14.3.1 [Reserved] RESERVED RESERVED RESERVED RESERVED None 14.3.2 Structural and NA NA NA See 14.2 Systems Engineering -

Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.3 Piping Systems and NA NA NA See 14.2 Components - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.4 Reactor Systems - NA NA NA See 14.2 Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.5 Instrumentation and NA NA NA See 14.2 Controls - Inspections, I I I I Page 78 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status Tests, Analyses, and Acceptance Criteria None 14.3.6 Electrical Systems - NA NA NA See 14.2.

Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.7 Plant Systems - NA NA NA See 14.2 Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.8 Radiation NA NA NA See 14.2 Protection - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.9 Human Factors NA NA NA See 14.2.

Engineering - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.10 Emergency NA NA NA See 14.2 Planning - Inspections, Tests, Analyses, and Acceptance Criteria None 14.3.11 Containment NA NA NA See 14.2 Systems - Inspections, Tests, Analyses, and Acceptance Criteria 14.3.12 Physical Security NA NA NA See 14.2 Hardware - Inspections, Tests, Analyses, and Acceptance Criteria Page 79 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s)

RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Chapter 15 - Accident Analyses

15. Accident Analyses 15.0 Introduction - None None NA Transient and Accident Analyses None 15.0.1 Radiological 2000 10 CFR 50.49, 50.67, App. A, None NA 10 CFR 50.67 does not apply to BLN. It is included to Consequence Analyses GDC 19, App. E, IV.E.8 highlight that BLN intends to utilize the Alternative Source Using Alternative Source 10 CFR 51 Term methodology.

Terms 10 CFR 20.1201 NUREG-0737, ll.B.2, ll.B.3, II.F.1, III.D.I.1, II1.A.1.2, III.D.3.4 RG 1.183 RO None 15.0.2 Review of Transient 2007 10 CFR 50.34, .46, App. B & K None NA The guidance in RG 1.203 RO will be used for any new and Accident Analysis NUREG-0737, I1.K.3.30 transient and accident analyses methods developed for use Method at BLN.

None 15.0.3 Design Basis 2007 10 CFR 50.34(a)(1) None NA Accident Radiological 10 CFR 50, App. A, GDC 19 Consequences of 10 CFR 50, App. E, IV.E.8 Analyses for Advanced 10 CFR 100, Subpart B Light Water Reactors None 15.1.1 - 15.1.4 Decrease 2007 10 CFR 50, App. A, GDCs - 10, None NA in Feedwater 13,15,20, 26 Temperature, Increase in RGs 1.53 R2, 1.105 R3 Feedwater Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve Page 80 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status None 15.1.5 Steam System 2007 10 CFR 50, App. A, GDCs 13,17, None NA Piping Failures Inside and 27, 28, 31,35 Outside of Containment NUREG 0737, I1.E.1.2, II.K.2.16, (PWR) II.K.3.5 BTP 3-3 App. B & BTP 3-4 None 15.1.5.A Radiological 1981 10 CFR 100, Subpart B None NA Consequences of Main RG 1.4 R2 Steam Line Failures Outside Containment of a PWR None 15.2.1 - 15.2.5 Loss of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA External Load; Turbine 15, 17, & 26 Trip; Loss of Condenser RGs 1.53 R2, 1.105 R3 Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed)

None 15.2.6 Loss of 2007 10 CFR 50, App. A, GDC 10, 13, None NA Nonemergency AC Power 15, 16, & 26 to the Station Auxiliaries RGs 1.53 R2, 1.105 R3 None 15.2.7 Loss of Normal 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Feedwater Flow 15, 17, 26 NUREG-0737,11.E.1.1, I1.E.1.2 RGs 1.53 R2, 1.105 R3 None 15.2.8 Feedwater System 2007 10 CFR 50, App. A, GDCs 13,17, None NA Pipe Breaks Inside and 25, 27, 28, 31,35 Outside Containment 10 CFR 100, Subpart B (PWR) NUREG-0737, II.E.1.1, II.E.1.2, II.K.2.16, BTPs 3-3 & 3-4 Page 81 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status None 15.3.1 - 15.3.2 Loss of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Forced Reactor Coolant 15, 17, 20, 26 Flow Including Trip of RGs 1.53 R2, 1.105 R3 Pump Motor and Flow Controller Malfunctions None 15.3.3 - 15.3.4 Reactor 2007 10 CFR 50, App. A, GDCs 17, 27, None NA Coolant Pump Rotor 28, & 31 Seizure and Reactor 10 CFR 100, Subpart B Coolant Pump Shaft Break NUREG-1465 None 15.4.1 Uncontrolled 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Control Rod Assembly 17, 20, & 25 Withdrawal from a Subcritical or Low Power Startup Condition None 15.4.2 Uncontrolled 2007 10 CFR 50, App. A, GDCs 10, 13, None NA Control Rod Assembly 17, 20, & 25 Withdrawal at Power None 15.4.3 Control Rod 2007 10 CFR 50, App. A, GDCs - 10, None NA misoperation (System 13, 20, & 25 Malfunction or Operator Error)

None 15.4.4 - 15.4.5 Startup of 2007 10 CFR 50, App. A, GDCs 10, 13, None NA an Inactive Loop or 15, 20, 26, 28 Recirculation Loop at an RGs 1.53 R2, 1.105 R3 Incorrect Temperature, and Flow Controller Malfunction Causing an Increase in BWR Core Flow Rate Page 82 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Status None 15.4.6 Inadvertent 2007 10 CFR 50, App. A, GDCs - 10, None NA Decrease in Boron 13, 15, &26 Concentration in the Reactor Coolant System (PWR)

None 15.4.7 Inadvertent Loading 2007 10 CFR 50, App. A, GDC 13 None NA and Operation of a Fuel 10 CFR 100, Subpart B Assembly in an Improper Position None 15.4.8 Spectrum of Rod 2007 10 CFR 50, App. A, GDCs 13 & None NA 10 CFR 50.67 does not apply to BLN. It is included to Ejection Accidents (PWR) 28, 50.67 highlight that BLN intends to utilize the Alternative Source 10 CFR 100, Subpart B Term methodology.

RGs 1.77 RO, 1.183 RO None 15.4.8.A Radiological 1981 10 CFR 100, Subpart B None NA Consequences of a RG 1.77 RO Control Rod Ejection Accident (PWR)

None 15.4.9 Spectrum of Rod NA to BLN - BWRs only Drop Accidents (BWR)

None 15.4.9.A Radiological NA to BLN - BWRs only Consequences of Control Rod Drop Accident (BWR)

None 15.5.1 - 15.5.2 Inadvertent 2007 10 CFR 50, App. A, GDCs 10, 13, None NA RIS 2005-29, Anticipated Transients that could Develop Operation of ECCS and 15 & 26 into More Serious Events Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory I I _I Page 83 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section K Ise Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria [diinlnomStatus None 15.6.1 Inadvertent 2007 10 CFR 50, App. A, GDC 10, 13, None NA Opening of a PWR 15, & 26 Pressurizer Pressure RGs 1.53 R2, 1.105 R3 Relief Valve or a BWR Pressure Relief Valve None 15.6.2 Radiological 1981 10 CFR 50, App. A, GDC 55 None NA Consequences of the 10 CFR 100, Subpart B Failure of Small Lines RG 1.11 R1 Carrying Primary Coolant Outside Containment None 15.6.3 Radiological 1981 10 CFR 100, Subpart B None NA Consequences of Steam RG 1.4 R2 Generator Tube Failure None 15.6.4 Radiological NA to BLN - BWRs only Consequences of Main Steam Line Failure Outside Containment (BWR)

None 15.6.5 Loss-of-Coolant 2007 10 CFR 50.46 None NA TVA will use an Appendix K compliant methodology in lieu Accidents Resulting From 10 CFR 50, App. A, GDC 13, 35 of the RG 1.157 best estimate methodology referenced in Spectrum of Postulated 10 CFR SU, App. K this SRP section.

Piping Breaks Within the 10 CFR 100, Subpart B Reactor Coolant Pressure NUREG-0737, I1.K.3.5, II.K.3.30, Boundary II.K.3.31 None 15.6.5.A Radiological 1981 10 CFR 100, Subpart B None NA Consequences of a RG 1.4 R2 Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution None 15.6.5.B Radiological 1981 10 CFR 100, Subpart B None NA For existing (legacy) equipment TVA will use RG 1.52 R1.

Consequences of a IIIFor newly procured/major modified equipment TVA will use Page 84 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan RG 1.70 (FSAR) Section NUREG 0800 (SRP)

Section SRP Revision SRP Section Acceptance Criteria Key Issue(s) KeyStatus Issue(s) Additional Information Design Basis Loss-of- RGs 1.4 R2, 1.7 R3, 1.52 RG 1.52 R4.

Coolant Accident: Leakage from Engineered Safety Feature Components Outside Containment None 15.6.5.D Radiological NA to BLN - BWRs only Consequences of a Design Basis Loss-of-Coolant Accident: Leakage from Main Steam Isolation Valve Leakage Control System (BWR)

None 15.7.3 Postulated 1981 10 CFR 20 None NA Radioactive Releases Due 10 CFR 50, App, A, GDC 60 to Liquid-Containing Tank Failures None 15.7.4 Radiological 1981 10 CFR 50, App. A, GDC 61 None NA Consequences of Fuel 10 CFR 100, Subpart B Handling Accidents RG 1.25 RO None 15.7.5 Spent Fuel Cask 1981 10 CFR 50. App. A. GDC 61 None NA Drop Accidents 10 CFR 100, Subpart B RG 1.25 RO None 15.8 Anticipated 2007 10 CFR 50.46, 62, App. A, GDCs None NA Transients Without Scram 12, 13, 14, 16, 35, 38, & 50 None 15.9 Boiling Water Reactor NA None NA NA to BLN - BWRs only Stability I Page 85 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Key Issue(s) Status Chapter 16 - Technical Specifications

16. Technical Specifications 16.0 Technical 2010 10 CFR 50.34(b)(6)(vi), 50.36, None NA The NUREG-1430 template will need to be modified for Specifications .36a digital safety-related instrumentation and control systems.

NUREG-1430 BLN intends to use the guidance contained in RG 1.93 RI relative to the availability of electric power sources.

16.1 Preliminary Technical 16.1 Risk-informed 2007 10 CFR 50, App. A, 50.36, 50.92 None NA Specifications Decision Making: RGs 1.174 R2, 1.177 R1 Technical Specifications 16.2 Proposed Final None Technical Specifications Page 86 of 91 TVA Letter dated October 10, 2012 Table I - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP Revision SRP Section Acceptance Criteria 1 Key Issue(s) Key Issue(s)

Status Additional Information RG 1.70 (FSAR) Section Section Chapter 17 - Quality Assurance

17. Quality Assurance None 17.1 Quality Assurance 17.1 Quality Assurance 1981 10 CFR 50, App. A & B, 50.55a, Temporary TVA submitted During Design and During the Design and 50.55(e) Cessation of QA the Quality Construction Construction RGs 1.8 R3, 1.26 R4, 1.29 R4 Program at BLN Verification ANSI/ANS-3.1-1978 Program (QVP)

BTPs - ASB 9.5-1 to NRC on 8/28/12.

17.1.1 Organization None 17.1.2 Quality Assurance None Program 17.1.3 Design Control None 17.1.4 Procurement None Document Control 17.1.5 Instructions, None Procedures, and Drawings 17.1.6 Document Control None 17.1.7 Control of None Purchased Material, Equipment, and Services 17.1.8 Identification and None Control of Materials, Parts, and Components 17.1.9 Control of Special None Processes 17.1.10 Inspection None 17.1.11, Test Control None Page 87 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP I R RP Section KeIsus) eysue)

RG 1.70 (FSAR) Section Section ]Revision Acceptance Criteria Status 17.1.12 Control of None Measuring and Test Equipment 17.1.13 Handling, Storage, None and Shipping 17.1.14 Inspection, Test, None and Operating Status 17.1.15 Nonconforming None Materials, Parts, or Components 17.1.16 Corrective Action None 17.1.17 Quality Assurance None Records 17.1.18 Audits None 17.2 Quality Assurance 17.2 1981 10 CFR 50, App. B None NA During the Operations ANSI N45.2.12 Phase None 17.3 Quality Assurance 1990 10 CFR 21, None NA Program Description i u CFR 50, App. A, Criterion i, App. B, .54(a)(3), .55a, .55(e),

.55(f)(3)

RGs 1.26 R4, 1.29 R4, 1.36 RO, 1.143 R2 ASME Code, Section 11, None 17.4 Reliability Assurance 2007 NA None NA TVA intends to complete a Level I and II PRA, as well as Program (RAP) meeting the requirements of 10CFR50.65, Maintenance Rule.

Page 88 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan RG 1.70 (FSAR) Section NUREG 0800 (SRP)

Section SRP Revision SRP Section Acceptance Criteria E 3e(s)

KeyStatus Issue(s) Additional Information None 17.5 Quality Assurance 2007 NA None NA Program Description -

Design Certification, Early Site Permit and New License Applicants None 17.6 Maintenance Rule 2007 10 CFR 50.59, 50.65, 50.65(a) None NA TVA does not intend to use 10 CFR 50.69 (which is RGs 1.160 R3, 1.187 RO addressed in this SRP section) with regard to risk-informed I I_categorization of SSCs.

Page 89 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Additional Information NRC00(S Rvin Acceptance Criteria Status RG 1.70 (FSAR) Section Section Rvso cetneCiei e su~)Sau Chapter 18 - Human Factors Engineering None 18.0 Human Factors 2007 10 CFR 50. 54(i) to (m), .120 Integrated HFE Developing plan TVA will use RG 1.97 R3 in lieu of R4.

Engineering 10 CFR 55 Plan, CRDR and and preparing to RGs 1.22 R0, 1.47 R1, 1.62 R1, redesign of the discuss with NRC 1.97 R3, 1.105 R3, 1.174 R2 control room NUREG-0737, I.C.5, I.D.1, I.D.2,11.E.1.2, I1.E.3.1, II.F.1, II.F.2, IlI.A.1.2, 111.D.3.3, NUREG-0696, 0700, 0711, 1342, 1764, 0835 None Appendix 18-A. Crediting 2009 10 CFR 50, App. B, Criteria II, III, Manual Operator Actions (For V, VI, .120 in Diversity and Defense- Commen BTP 7-19 in-Depth (D3) Analyses t) NUREG -0711 Page 90 of 91 TVA Letter dated October 10, 2012 Table 1 - BLN Conformance with the NRC Standard Review Plan NUREG 0800 (SRP) SRP SRP Section Key Issue(s) Key Issue(s) Additional Information RG 1.70 (FSAR) Section Section Revision Acceptance Criteria Adiinl nomStatus Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors None 19.0 Probabilistic Risk 2007 10 CFR 50.34(f)(1)(i), App. B Use GMRS Using Seismic PRA to address "above design basis Assessment and Severe RGs 1.174 R2, 1.200 R2 based on new spectra" is identified as an acceptable approach in 50.54(f)

Accident Evaluation for ASME/ANS RA-Sa-2009 Addenda hazard model letter issued on March 12, 2012.

New Reactors to ASME/ANS RA-S-2008 (2012 CEUS) to TVA does not intend to use 10 CFR 50.69 (which is perform Seismic addressed in this SRP section) with regard to risk-informed PRA. categorization of SSCs.

None 19.1 Determining the 2012 RGs 1.174 R2,1.200 R2 Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities None 19.2 Review of Risk NA - Operating plants Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance Page 91 of 91 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 71-01 Involves Main Steam Isolation Valves NA BWR IEB 71-02 No Title - Involves PWR Reactor Trip NA Addressed to specific plant(s).

Circuit Breakers IEB 71-03 No Title - Involves Catastrophic Failure of NA Addressed to specific plant(s).

Main Steam Line Relief Valve Headers IEB 72-01 Failed Hangers for Emergency Core NA Addressed to specific plant(s).

Cooling System Suction Header IEB 72-02 Simultaneous Actuation of a Safety NA Addressed to specific plant(s).

Injection Signal on Both Units of a Dual Unit Facility IEB 72-03 Limitorque Valve Operator Failures NA Addressed to specific plant(s).

IEB 73-01 Faulty Overcurrent Trip Delay Device in Closed No specific actions will be taken; instead, the electrical equipment Circuit Breakers for Engineered Safety will be either refurbished or replaced as part of the QVP.

Systems IEB 73-02 Malfunction of Containment Purge Supply Closed No specific actions will be taken; instead, the system will be Valve Switch evaluated for failure modes and effects as part of the design completion activities.

IEB 73-03 Defective Hydraulic Snubbers and Closed No specific actions will be taken; instead, the installed snubbers will

!EB 73-04 I Restraints Defecive Bege- Pattersoon... ,. .. ,^ r,^ be either refurbished or replaced as part of the QVP.

.... e, , *, ou No specific actions wiii be taken; instead, the installed snubbers will Shock Absorbers be either refurbished or replaced as part of the QVP.

IEB 73-05 Manufacturing Defect in BWR Control NA BWR Rods IEB 73-06 Inadvertent Criticality in a BWR NA BWR IEB 74-01 Valve Deficiencies Closed No specific actions will be taken; instead, installed valves will be either refurbished or replaced as part of the QVP.

IEB 74-02 Truck Strike Possibility NA Information IEB 74-03 Failure of Structural or Seismic Support NA Not applicable to BLN. The letter was addressed to all plants with Bolts on Class I Components I current operating licenses and those with fuel load prior to 1/31/75.

Page 1 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 74-04 Malfunction of Target Rock Safety Relief NA BWR

& 4a Valves IEB 74-05 Shipment of an Improperly Shielded NA Does not apply to power reactors Source IEB 74-06 Defective Westinghouse Type W-2 Control Closed No specific actions will be taken; instead, the installed control room Switch Component switches will be replaced as part of the QVP.

IEB 74-07 Personnel Exposure - Irradiation Facility NA Does not apply to power reactors IEB 74-08 Deficiency in the ITE Molded Case Circuit Closed No specific actions will be taken; instead, the installed breakers will Breakers, Type HE-3 be either refurbished or replaced as part of the QVP.

IEB 74-09 Deficiencies in GE Model 4KV Magne- Closed There is no 4KV system at BLN.

Blast Circuit Breakers IEB 74-10 Failures in 4 inch Bypass Pipe at Dresden NA BWR IEB 74-11 Improper Wiring of Safety Injection Logic NA Westinghouse at Zion 1 & 2 IEB 74-12 Incorrect Coils in W Type SG Relays at Closed No specific actions will be taken; instead, the installed safety-related Trojan electrical equipment will be either refurbished or replaced as part of the QVP.

IEB 74-13 Improper Factory Wiring on GE Motor Closed There are no GE motor control centers at BLN.

Control Centers at Fort Calhoun

• 7-1 BRyvlx,Relief volve iouIsharge to NA BVVR Suppression Pool IEB 74-15 Misapplication of Cutler-Hammer Three Closed No specific actions will be taken; instead, the installed control room Position Maintained Switch Model No. switches will be replaced as part of the QVP.

10250T IEB 74-16 Improper Machining of Pistons in Colt NA The Diesel Generators at BLN are Model DSRV-16-4 manufactured Industries (Fairbanks-Morse) Diesel by Transamerica DeLaval Company (TDI). Since Fairbanks Morse is Generators not the manufacturer of the DGs, IEB 74-16 is not applicable to BLN.

IEB 75-01 Through-Wall Cracks in Core Spray Piping NA BWR I at Dresden-2 II Page 2 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 75-02 Defective Radionics Radiograph Exposure NA Does not apply to power reactors Devices and Source Changes IEB 75-03 Incorrect Lower Disc Spring and Closed No specific actions will be taken; instead, the installed equipment will Clearance Dimension in Series 8300 and be refurbished or replaced as part of the QVP.

8302 ASCO Solenoid Valves IEB 75-04 Cable Fire at BFNPP Closed Implementation of the Fire Protection program will result in compliance with the guidance contained in R.G.'s 1.189 and 1.205, and with the issues addressed in this bulletin.

IEB 75-05 Operability of Category I Hydraulic Shock Closed No specific actions will be taken; instead, the installed equipment will and Sway Suppressors be refurbished or replaced as part of the QVP.

IEB 75-06 Defective W Type OT-2 Control Switches Closed TVA stated in a 7/31/75 letter that no OT-2 switches are planned for use at BLN and NRC closed the IEB in IR 438/439/75-7.

IEB 75-07 Exothermic Reaction in Radwaste NA Does not apply to power reactors Shipment IEB 75-08 PWR Pressure Instrumentation Closed TVA will use the guidance in SRP 7.5 as part of the design completion activities.

IEB 76-01 BWR Isolation Condenser Tube Failure NA BWR IEB 76-02 Relay Coil Failures Closed No specific actions will be taken; instead, the installed equipment will be replaced as part of the QVP.

76-03 Relay

,E Malfunctions - GE Type STD Closed See IEB 76-02.

Relays IEB 76-04 Cracks in Cold Water Piping at BWRs NA BWR IEB 76-05 Relay Failures Closed TVA letter dated 6/7/76 stated that the relays in question were not used in safety related circuits at BLN. NRC closed this IEB in their letter dated 8/18/76.

IEB 76-06 Diaphragm Failures in Air Operated Closed No specific actions will be taken; instead, the installed valve Auxiliary Actuators for Safety/Relief Valves actuators will be replaced as part of the QVP.

IEB 76-07 Crane Hoist Control Circuit Modifications Closed TVA stated in a letter dated 10/29/76 that due to differences in brake I_ I design, no action was required at BLN.

IEB 76-08 Teletherapy Units NA Does not apply to power reactors Page 3 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 77-01 Pneumatic Time Delay Relay Setpoint Drift Closed TVA letter dated 7/1/77 states that BLN does not use these relays.

IEB 77-02 Potential Failure Mechanism in Certain W Closed TVA letter dated 11/11/77 stated that "no relays of the type identified AR Relays with Latch Attachments as a potential problem have been used or are planned for use in safety related circuits at BLN."

IEB 77-03 On-Line Testing of the W Solid State NA Applies to Westinghouse units only.

Protection System IEB 77-04 Calculation Error Affecting Performance of Closed TVA will evaluate the post-LOCA containment emergency sump a System for Controlling pH of water pH using the guidance in SRP Section 6.1.1 and BTP 6-1 as Containment Sump Water Following a part of the design completion activities.

LOCA IEB 77-05 Electrical Connector Assemblies Closed This Bulletin is addressed by the BLN EQ Program, which will meet the requirements of 10 CFR 50.49 using the guidance of SRP Section 3.11 as part of the design competition activities.

IEB 77-06 Potential Problems with Containment NA Applicable to licensed plants Electrical Penetration Assemblies IEB 77-07 Containment Electrical Penetration Closed No specific actions will be taken; instead, the installed penetration Assemblies at Nuclear Power Plants under assemblies will be replaced or refurbished as part of the QVP.

Construction IE 77-08 Assurance of Safety and Safeguards Closed TVA will implement a physical security plan as required by 10 CFR During an Emergency - Locking Systems 73.55 and using the guidance of SRP 13.6.1 as part of the piant completion activities.

IEB 78-01 Flammable Contact - Arm Retainers in GE Closed TVA letter dated 3/20/78 states that none of the relays of the type CR120A Relays described in the bulletin are installed or scheduled to be installed at BLN.

IEB 78-02 Terminal Block Qualification Closed TVA letter of 3/1/78 stated that BLN did not use, or plan to use, unprotected terminal blocks in systems which must function in a post accident environment.

IEB 78-03 Potential Gas Mixture Accumulations NA BWR Associated with BWR Offgas System Operations Page 4 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 78-04 Environmental Qualification of Certain Closed This Bulletin is addressed by the BLN EQ Program, which will meet Stem Mounted Limit Switches Inside the requirements of 10 CFR 50.49 using the guidance of SRP Reactor Containment Section 3.11 as part of the design competition activities.

IEB 78-05 Malfunctioning of Circuit Breaker Auxiliary Closed TVA letter dated 6/12/78 stated that TVA "neither uses nor do we Contact Mechanism plan to use circuit breaker auxiliary contact mechanisms of the type described by IEB 78-01 in Class 1E circuits of the subject plants."

The subject plants include BLN.

IEB 78-06 Defective Cutler-Hammer Type M Relays Closed TVA letter dated 7/31/78 stated that "TVA does not now use or plan and DC Coils to use the C-H D23 MRD relays in safety related systems for BLN."

IEB 78-07 Protection Afforded by Air-Line NA Applicable to licensed plants Respirators and Supplied-Air Hoods IEB 78-08 Radiation Levels from Fuel Element NA Applicable to licensed plants Transfer Tubes IEB 78-09 BWR Drywell Leakage Paths Associated NA BWR with Inadequate Drywell Closures IEB 78-1,0 Bergen-Patterson Hydraulic Shock Closed No specific actions will be taken; instead, the installed snubbers will Suppressor Accumulator Spring Coils be replaced or refurbished as part of the QVP.

IEB 78-11 Examination of Mark I Containment Torus NA BWR Welds E. 78-12 Atypical Weld

. Matrial in Reactor Closed& submitted a generic report entiiled "Records investigation Pressure Vessel Welds Report Related to Off-Chemistry Welds in Material Surveillance Specimens and Responses to Bulletin 78-12 and 78-12a Supplement" (see letter from James Taylor - B&W to G. Reinauth -

NRC dated 3/13/1979). The letter states that off-chemistry conditions were discovered in a reactor vessel surveillance specimen for the CR-3 plant, but it is very unlikely that other similar conditions exist in any reactor pressure vessel welds. By letter to the NRC dated 5/29/79, TVA endorsed these conclusions relative to the BLN reactor pressure vessels. No further action is required.

Page 5 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 78-13 Failures in Source Heads Kay Ray Gauge NA Does not apply to power reactors Models 7050, 7050B, 7051, 7051B, 7060, 7060B, 7061 and 7061B IEB 78-14 Deterioration of Buna-N Components in NA BWR ASCO Solenoids IEB 79-01 Environmental Qualification of Class 1 E Closed This Bulletin is addressed by the BLN EQ Program, which will meet Equipment the requirements of 10 CFR 50.49 using the guidance of SRP Section 3.11 as part of the design competition activities.

IEB 79-02* Pipe Support Base Plate Designs Using Closed TVA will evaluate pipe support base plate designs using concrete Concrete Expansion Anchor Bolts expansion anchor bolts using the guidance in SRP Section 3.12 as part of the design completion activities.

IEB 79-03 Longitudinal Weld Defects in ASME SA- Closed No SA-312 or A-312 Type 300 Series fusion weld piping was used at 312 Type 304 SS Pipe Spools Fabricated BLN, as stated in the 07/02/81 TVA letter. NRC closed this IEB in IR by Youngstown Welding & Engineering 438/439/80-2.

IEB 79-04 Incorrect Weights for Swing Check Valves Closed Per TVA response to IEB 79-04 (5/31/79), no 3, 4, or 6 inch Velan Manufactured by Velan Engineering check valves are installed at BLN nor were they scheduled for installation in any seismic Category 1 piping system. NRC closed this IEB in IR 438/439/80-2.

IEB 79-05 Nuclear Incident at TMI Closed The lessons learned from TMI are addressed in the applicable TMI items referenced in Table 1.

IEB 79-06 Review of Operational Errors and System NA Not addressed to B&W plants.

Misalignments Identified During the Three Mile Island Incident IEB 79-07 Seismic Stress Analysis of Safety-Related Closed Per the TVA response to IEB 79-07 in 5/31/79 letter, the seismic Piping analysis performed for BLN was free from the deficiencies summarized in this IEB. NRC closed this IEB in IR 438/439/79-20.

IEB 79-08 Events Relevant to BWRs Identified NA BWR During TMI Incident IEB 79-09 Failure of GE Type AK-2 Circuit Breaker in Closed No specific actions will be taken; instead, the installed electrical Safety Related Systems equipment will be replaced or refurbished as part of the QVP.

IEB 79-10 Requalification Training Program Statistics NA Applicable only to operating plants.

Page 6 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units i & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 79-11 Faulty Overcurrent Trip Device in Circuit Closed TVA letter dated 7/20/79 stated that "none of the DB 50 and DB 75 Breakers for Engineering Safety Systems circuit breakers with over-current trip devices have been used or are planned for use at BLN. NRC closed this item in IR 438/439/79-20 dated 8/31/79.

IEB 79-12 Short Period Scrams at BWR Facilities NA BWR IEB 79-13* Cracking in Feedwater Piping Closed TVA will implement the in-service inspection requirements of the ASME Code as required by 10 CFR 50.55a using the guidance in SRP Section 10.4.7 as part of the plant completion activities.

IEB 79-14 Seismic Analysis for As-Built Safety- Closed See IEB 79-02.

Related Piping Systems IEB 79-15 Deep Draft Pump Deficiencies Closed No specific actions will be taken; instead, the Core Spray and Decay Heat Removal Pumps will use the guidance in SRP 6.2.2 and 6.3 as part of the design completion activities..

IEB 79-16 Vital Area Access Controls Closed TVA will implement a physical security plan as required by 10 CFR 73.55 and using the guidance of SRP Section 13.6.1 as part of the plant completion activities.

IEB 79-17 Pipe Cracks in Stagnant Borated Water NA Applicable to licensed plants Systems at PWR Plants IEB 79-18 Audibility Problems Encountered on NA Applicable to licensed plants Evacuation of Personnel from High-Noise Areas IEB 79-19 Packaging of Low-Level Radioactive NA Applicable to licensed plants Waste for Transport and Burial IEB 79-20 Packaging, Transport and Burial of Low- NA Applicable to licensed plants Level Radioactive Waste IEB 79-21 Temperature Effects on Level Closed TVA will address temperature effects of temperature on level Measurements measurements using the guidance in SRP Sections 7.2 and 7.3 along with BTP 7-12 as part of the design completion activities.

IEB 79-22 Possible Leakage of Tubes of Tritium Gas NA Does not apply to power reactors.

Used in Time Pieces for Luminosity I __I Page 7 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 79-23 Potential Failure of Emergency Diesel Closed No specific actions will be taken; instead, the transformers will be Generator Field Exciter Transformer replaced or refurbished as part of the QVP.

IEB 79-24* Frozen Lines Closed TVA will address the potential for frozen lines using the guidance in SRP Section 6.3 as part of the design completion activities.

IEB 79-25 Failures of W BFD Relays in Safety Closed In a letter from TVA to NRC dated 1/4/80, it was stated that "TVA's Related Systems investigation revealed that none of the Westinghouse BFD or NBFD relays are in use, or are planned for use, in safety-related systems at BLN." NRC closed this bulletin in IR 438,439/80-02 dated 2/6/80.

IEB 79-26 Boron Loss from BWR Control Blades NA BWR

& R1 IEB 79-27 Loss of Non-Class 1E I & C Power System Closed See GL 80-18.

Bus During Operation IEB 79-28 Possible Malfunction of NAMCO Model Closed TVA stated in a 3/28/80 letter that no NAMCO switches with the EA180 Limit Switches at Elevated referenced date code were identified in safety related components at Temperatures BLN. NRC closed this IEB in IR 438/439/80-08.

IEB 80-01 Operability of ADS Valve Pneumatic NA BWR Supply IEB 80-02 Inadequate QA for Nuclear Supplied NA BWR iiER 80-03" - Equipment

,o* ha at-m ÷ , ., Type.. ,* 1 Closed..:,

Loss of Charcoal from Standard . 2 C Ty VA will use the NUREG-1430 B&W STS for the development of the Inch Tray Adsorber Cells BLN Technical Specifications and RG 1.52 for the development of the Ventilation Filter Testing Program. In addition all ventilation filters will be either replaced or refurbished as a part of the QVP.

IEB 80-04 Analysis of a PWR Main Steam Line Closed TVA will address the mass and energy release analysis for Rupture with Continued Feedwater postulated secondary system pipe ruptures using the guidance in Addition SRP Section 6.2.1.4 as part of the design completion activities.

IEB 80-05* Vacuum Condition Resulting in Damage to Closed TVA will address the vacuum conditions for Chemical Volume Chemical Volume Control System Holdup Control System Holdup Tanks using the guidance in SRP Section Tanks 9.3.4 as part of the design completion activities.

Page 8 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 80-06 Engineered Safety Features Reset Control Closed TVA will address the ESF reset design using the guidance in SRP Sections 7.1-A, 7.1-C, and 7.1-D as part of the design completion activities.

IEB 80-07 BWR Jet Pump Assembly Failure NA BWR IEB 80-08* Examination of Containment Liner Closed TVA will implement the in-service inspection requirements of the Penetration Welds ASME Code as required by 10 CFR 50.55a using the guidance in SRP Section 3.8.2 as part of the plant completion activities.

IEB 80-09 Hydramotor Actuator Deficiencies Closed TVA determined that BLN had the subject actuators and subsequently satisfactorily responded to the IEB required actions.

NRC letter dated 7/11/89 (NUREG/CR-5291) confirms the item as closed.

IEB 80-10* Contamination of Non-radioactive System Closed TVA will design the decay heat removal system using the guidance and Resulting Potential for Unmonitored, of SRP Section 11.2 as part of the design competition activities.

Uncontrolled Release of Radioactivity to Environment IEB 80-11 Masonry Wall Design Closed TVA will design masonry walls using the guidance:of SRP Section 3.8.4 as part of the design competition activities.

IEB 80-12 Decay Heat Removal System Operability Closed TVA will design the decay heat removal system using the guidance of SRP Section 5.4.7 as part of the design competition activities.

!E9 80-13 Cracking in Core Spray NA

, vvR IEB 80-14 Degradation of Scram Discharge Volume NA BWR Capability IEB 80-15 Possible Loss of Emergency Notification Closed TVA will develop the emergency response plans using the guidance System with Loss of Offsite Power of SRP Section 13.3 as part of the plant competition activities.

IEB 80-16 Potential Misapplication of Rosemount Closed TVA letter dated 8/29/80 stated that no situation existed wherein the Models 1151 and 1152 Pressure anomalous output could occur at BLN. NRC IR 50-438/81-06 and 50-Transmitters With Either "A" or "D" Output 439/81-06 dated 3/6/81 closed this bulletin.

Codes I IEB 80-17 Failure of 76 of 185 Control Rods to Fully NA BWR Insert During a Scram at a BWR I Page 9 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 80-18* Maintenance of Adequate Minimum Flow Closed TVA will design the ECCS using the guidance of SRP Section 6.3 as Thru Centrifugal Charging Pumps part of the design completion activities.

Following a Secondary Side High Energy Rupture IEB 80-19 Mercury-Wetted Matrix Relay in Reactor Closed NUREG/CR-4933 stated that BLN did not use subject relays and

& R1 Protective Systems bulletin was closed for BLN. Additionally, the new Areva digital architecture will replace the original RPS systems and the new RPS equipment will not utilize mercury wetted relays.

IEB 80-20 Failure of W Type W-2 Spring Return to Closed No specific actions will be taken; instead, the electrical equipment Neutral Control Switches will be either refurbished or replaced as part of the QVP.

IEB 80-21 Valve Yokes Supplied by Malcolm Closed TVA stated in a letter dated 5/6/81 that no valve parts made by Foundry Co. Malcolm Foundry were used or planned for use at BLN. NRC closed this IEB in IR 438/439/81-23 IEB 80-22 Automation Industries, Model 200-520-008 NA Does not apply to power reactors Sealed-Source Connectors IEB 80-23 Failures of Solenoid Valves Manufactured Closed TVA stated in a letter dated 3/31/81 that BLN does not have the by Valcor Eng. Corp Valcor valves with the subject P/Ns. NRC closed this IEB in IR 438/439/81-15.

IEB 80-24 Prevention of Damage Due to Water Closed TVA will design the leakage detection system using the guidance of Leakage Inside Containment SRP Section 5.2.5 as pari or the design completion activities.

IEB 80-25 Operating Problems with Target Rock SR NA BWR Valves at BWRs IEB 81-01 Surveillance of Mechanical Snubbers NA BLN is not listed among plants to provide response to this IEB.

IEB 81-02 Failure of Gate Type Valves to Close Closed TVA response letter dated 4/13/82 addressed this IEB for BLN.

& 51 Against Differential Pressure IEB 81-03 Flow Blockage to Cooling Water by Asiatic Closed TVA will implement a service water monitoring program using the Clams and Mussels guidance of SRP Section 9.2.1 as part of the plant completion activities.

IEB 82-01 Alterations of Radiographs of Welds in NA Not applicable to BLN per absence of BLN in Table 1 of IEB 82-01.

Piping Subassemblies I __I Page 10 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 82-02 Degradation of Threaded Fasteners in the Closed TVA will evaluate the reactor coolant pressure boundary using the Reactor Coolant Pressure Boundary of guidance in SRP Section 3.13 as part of the design completion PWR Plants activities.

IEB 82-03 Stress Corrosion Cracking in Thick-Wall, NA BWR Large Diameter, Stainless Steel, Recirculation System Piping at BWR Plants IEB 82-04 Deficiencies in Primary Containment Closed TVA letter to the NRC, dated 01/24/1983, reported that no TVA Electrical Penetration Assemblies plants, including BLN, had purchased or used any Bunker Ramo Company electrical penetration assemblies. NRC closed this bulletin in IR 50-438/83-08 and 50-439/83-08 dated 4/14/83.

IEB 83-01 Failure of Trip Breakers (Westinghouse Closed The BLN design will not utilize Westinghouse DB-50 Reactor Trip DB-50) to Open on Automatic Trip Signal Breakers in its RPS.

IEB 83-02 Stress Corrosion Cracking in Large- NA BWR Diameter Stainless Steel Recirculation System Piping at BWR Plants IEB 83-03 Check Valve Failures in Raw Water Closed TVA will implement the in-service testing requirements of the ASME Cooling Systems of Diesel Generators Code as required by 10 CFR 50.55a in accordance with NUREG-1430 B&W STS as part of the plant completion activities.

IEB 83-04 Failure of the Undervo!tage Trip Function Closed See GL 83-28.

Breakers of Reactor Trip IEB 83-05 ASME Nuclear Code Pumps and Spare Closed No specific actions will be taken; instead, the installed pumps and Parts Manufactured by Hayward Tyler pump spare parts will be replaced or refurbished as part of the QVP.

Pump Co IEB 83-06 Nonconforming Material Supplied by Closed Final WVA response on 2/2/84 stated that all corrective action, Tube-Line including removal and replacement of suspect fittings, will be completed by December 1984. NRC Inspection report 84-22, dated 10/31/84 stated that NRC closed this IE Bulletin after reviewing supporting documentation and observing representative samples of work to verify that the actions identified in the TVA letter had been completed.

Page 11 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 83-07 Apparently Fraudulent Products Sold by Closed IE Bulletin 83-07 was closed in NRC Inspection report (IR)

Ray Miller, Inc 438,439/84-22 based on TVA letter dated 3/22/84, review of supporting documentation, and observing representativesamples of work to verify that the actions identified in the letter had been completed.

IEB 83-08 Electrical Circuit Breakers With Closed TVA letter dated 03/29/1984 informed NRC that the required actions Undervoltage Trip in Safety Related for BLN were complete. The letter stated that breakers with an Applications other than the Reactor Trip undervoltage trip attachment feature have not been specified for use System on safety-related systems exclusive of the reactor trip system. The NRC addressed closure of this bulletin in Inspection Report 438/439 86-04.

IEB 84-01 Cracks in BWR Mark 1 Containment Vent NA BWR Headers IEB 84-02 Failure of GE Type HFA Relays In Use In Closed TVA letter dated 07/10/1984 informed NRC that the actions for BLN Class 1E Safety Systems had been completed. The letter stated that per B&W letter D-4791 dated 10/6/83, no GE type HFA relays have been supplied or specified by B&W for use in any of the NSSS 1 E safety systems supplied to BLN. The NRC addressed closure of this bulletin in Inspection Report 438/439 86-04.

IEB 84-03* Refueling Cavity WA/Pter Seal Clnsed TVA will evaluate the reactor cavity.. uiy . the guidadsce u*ug of SRP Section 9.1.2 as part of the design completion activities.

IEB 85-01* Steam Binding of Auxiliary Feedwater Closed TVA will evaluate the potential steam binding of Auxiliary Feedwater Pumps Pumps using the guidance of SRP Section 10.4.9 as part of the design completion activities.

IEB 85-02 Undervoltage Trip Attachment of W DB-50 Closed See GL 83-28.

Type Reactor Trip Breakers IEB 85-03 Motor Operated Valve Common Mode Closed See GL 89-10.

Failures During Plant Transients due to Improper Switch Settings IEB 86-01 Minimum Flow Logic Problems That Could NA BWR Disable RHR Pumps Page 12 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 86-02 Static "0" Ring Differential Pressure Closed- TVA response on 11/20/86 stated that no such switches are installed Switches or currently planned for installation at BLN. Therefore, no additional actions are required.

IEB 86-03 Potential Failure of Multiple ECCS Pumps Closed TVA response on 11/14/86 states "In summary, the single failure Due to Single Failure of Air-Operated vulnerability discussed in the subject bulletin does not exist at BLN."

Valve in Minimum Flow Recirculation Line NRC closed this IEB in IR 438/439/86-09.

IEB 86-04 Defective Teletherapy Timer That May Not NA Does not apply to power reactors Terminate Treatment Dose IEB 87-01 Thinning of Pipe Walls in Nuclear Power Closed See GL 89-08.

Plants IEB 87-02 Fastener Testing to Determine Closed In a letter dated August 18, 1989, the NRC stated that, "We conclude Conformance with Applicable Material that you have satisfactorily addressed the requirements for Specifications responding to NRC Bulletin 87-02. This closes out our review of your responses to the Bulletin." No follow up requirements or additional field inspections were required by the NRC inspector.

IEB 88-01* Defects in W Circuit Breakers Closed No specific actions will be taken; instead, the electrical equipment will be either refurbished or replaced as part of the QVP.

IEB 88-02 Rapidly Propagating Fatigue Cracks in NA NA for B&W plants. Applicable to Westinghouse SGs and Steam Generator Tubes information only for CE plants.

.F..... Ind.... ate Latch

... Engagement in CoS ed TvA l.ter dated 7/161/188 states that "BBLN does not have GE HFA-type Type Latching Relays Manufactured by latching relays" as described in this IEB. Also, see response to IEB General Electric (GE) Company 84-02.

IEB 88-04* Potential Safety-Related Pump Loss Closed TVA will design the ECCS using the guidance of SRP Section 6.3 as part of the design completion activities.

Page 13 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 88-05 Nonconforming Materials Supplied by Open TVA will:

Piping Supplies, Inc. and West Jersey 1) Review purchasing records to determine if any ASME Code or Manufacturing Company ASTM materials (flanges and fittings only) were supplied to BLN by PSI, WJM, or CLM (see IEB 88-05 Supplement 2) and, if so,

2) Ensure compliance with appropriate requirements by document verification, replacement of components or in-situ testing, and maintain documentation of the specific actions taken.

3) Quarantine non-conforming materials.

4) Report results of the records review, testing, and analysis to NRC prior to fuel load.

IEB 88-06 Actions to be Taken for the Transfer of NA Does not apply to power reactors Model No. SPEC 2-T Radiographic Exposure Device IEB 88-07 Power Oscillations in BWRs NA BWR IEB 88-08* Thermal Stresses in Piping Connected to Closed TVA will evaluate thermal stresses using the guidance in SRP Reactor Cooling Systems Sections 3.9.3 and 3.12 as part of the design completion activities.

IEB 88-09 Thimble Tube Thinning in Westinghouse NA Not applicable to B&W plants.

Reactors IEB 88-10 Nonconforming Molded-Case Circuit Closed No specific actions will be taken; instead, the electrical equipment

....... eiter

,Wbe reuhrbishd ,.,,iaced as part of te QVP.

IEB 88-11" Pressurizer Surge Line Thermal Closed TVA will evaluate pressurizer surge line thermal stratification using Stratification the guidance in SRP Section 3.9.3 and 3.12 as part of the design completion activities.

IEB 89-01 Failure of Westinghouse Steam Generator Closed BLN steam generators are being replaced, and Alloy 600TT material Tube Mechanical Plugs is no longer used for tube plugs.

IEB 89-02 Stress Corrosion Cracking of High- Closed TVA will evaluate ASME Code threaded fasteners using the Hardness Type 410 Stainless Steel guidance in SRP Section 3.13 as part of the design completion Preloaded Bolting in Anchor Darling Model activities.

S350W Swing Check Valves or Valves of Similar Nature Page 14 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 89-03 Potential Loss of Required Shutdown Closed TVA will evaluate the required fuel assembly configurations using the Margin During Refueling Operations guidance in SRP Section 9.1.1 as part of the design completion activities.

IEB 90-01 Loss of Fill-Oil in Transmitters Closed No specific actions will be taken; instead, the electrical equipment Manufactured by Rosemount will be either refurbished or replaced as part of the QVP.

IEB 90-02 Loss of Thermal Margin Caused by NA BWR Channel Box Bow IEB 91-01 Reporting Loss of Criticality Safety NA Does not apply to power reactor Controls IEB 92-01 Failure of Thermo-Lag 330 Fire Barrier Closed TVA will use the guidance of SRP Section 9.5.1.1 and R.G. 1.189 R1 System To Maintain Cabling in Wide in the design of any fire protection barriers as part of the design Cable Trays and Small Conduits Free from completion activities.

Fire Damage & to Perform its Specified Fire Endurance Function IEB 92-02 Safety Concerns Related to "End of Life" NA Does not apply to power reactors of Aging Theratronics Teletherapy Units IEB 92-03 Release of Patients after Brachytherapy NA Does not apply to power reactors IEB 93-01 Release of Patients After Brachytherapy NA Does not apply to power reactors Treatment With Remote Afterloading Devices IEB 93-02 Debris Plugging of Emergency Core NA BWR Cooling Suction Strainers IEB 93-03 Resolution of Issues Related to Reactor NA BWR Vessel Water Level Instrumentation in BWRs IEB 94-01 Potential Fuel Pool Draindown Caused by NA Addressed to holders of licenses for power reactors that are Inadequate Maintenance Practices at permanently shut down with spent fuel in the pool.

Dresden IEB 94-02 Corrosion Problems in Certain Stainless NA Does not apply to power reactors Steel Packagings Used to Transport Uranium Hexafluoride Page 15 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure IEB 95-01 Quality Assurance Program for NA Does not apply to power reactors Transportation of Radioactive Material IEB 95-02 Unexpected Clogging of a Residual Heat NA BWR Removal (RHR) Pump Strainer While Operating In Suppression Pool Cooling Mode IEB 96-01 Control Rod Insertion Problems (PWR) NA For information only for B&W and CE plants.

IEB 96-02 Movement of Heavy Loads over Spent Closed TVA will ensure that plant design satisfies the guidance in SRP Fuel, over Fuel in the Reactor, or over Section 9.1.5 and NUREG-0612 as part of the design completion Safety-Related Equipment activities.

IEB 96-03 Potential Plugging of ECCS Suction NA BWR Strainers by Debris in BWRs IEB 96-04 Chemical, Galvanic or Other Reactions in NA Information Spent Fuel Storage and Transportation Casks IEB 97-01 Potential for Erroneous Calibration, Dose NA Does not apply to power reactors Rate, or Radiation Exposure Measurements with Certain Victoreen Model 530 and 531SI Electrometers, Dose Meters IEB 97-02 Puncture Testing of Shipping Packages NA Does not apply to power reactors Under 10 CFR Part 71 IEB 01-01 Circumferential Cracking of Reactor Closed TVA will implement the in-service inspection requirements of the Pressure Vessel (RPV) Head Penetration ASME Code as required by 10 CFR 50.55a using the guidance in Nozzles SRP Section 5.2.4 as part of the plant completion activities.

IEB 02-01 RPV Head Degradation and Reactor Closed TVA will implement the in-service inspection requirements of the Coolant Pressure Boundary Integrity ASME Code as required by 10 CFR 50.55a using the guidance in SRP Section 5.2.4 as part of the plant completion activities.

IEB 02-02 RPV Head and Vessel Head Penetration Closed See IEB 01-01 Nozzle Inspection Program Page 16 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title ] BLN Status TVA Action to be Completed or Justification for Closure IEB 03-01 Potential Impact of Debris Blockage on Closed See USI A-43, Containment Emergency Sump Performance.

Emergency Sump Recirculation IEB 03-02 Leakage from RPV Lower Head Closed TVA will implement the in-service inspection requirements of the Penetrations and Reactor Coolant ASME Code as required by 10 CFR 50.55a using the guidance in Pressure Boundary Integrity SRP Section 5.2.4 as part of the plant completion activities.

IEB 03-03 Potentially Deficient 1-inch Valves for NA Does not apply to power reactors Uranium Hexaflouride Cylinders IEB 03-04 Rebaselining of Data in the Nuclear NA No special nuclear material is currently on site nor will there be any Management and Safeguards System on site for several years.

IEB 04-01 Inspection of Alloy 82/182/600 Materials Closed TVA will implement the in-service inspection requirements of the Used in the Fabrication of Pressurizer ASME Code as required by 10 CFR 50.55a using the guidance in Penetrations and Steam Space Piping SRP Section 5.2.4 as part of the plant completion activities.

Connections at PWRs IEB 05-01 Material Control and Accounting of NA NA for CP holder.

Reactors and Spent Fuel Storage Facilities IEB 05-02 Emergency Preparedness and Response NA BLN will not have an OL for several years.

Actions for Security Based Events IEB 07-01 Security Officer Attentiveness Closed TVA will implement a physical security plan as required by 10 CFR 73.

I 55a, Cl ul sing an4 I.W/

O.1,1. y the guianc LII* *:UI~dll ... I :In Sr*P 13.1.

lljI~~F I~)O as~ ~pairt IL of ~II ILI the plant completion activities.

IEB 11-01 Mitigating Strategies NA Applicable to licensed plants IEB 12-01 Design Vulnerability in Electric Power NA Applicable to licensed plants System GL 77-01 Intrusion Detection Systems Handbook NA Information GL 77-02 Fire Protection Functional Responsibilities NA Information GL 77-03 Transmittal of NUREG-0321, "A Study of NA Information the Nuclear Regulatory Commission Quality Assurance Program" Page 17 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 77-04 Shipments of Contaminated Components NA Information From NRC Licensed Nuclear Power Facilities to Vendors & Service Companies GL 77-05 Nonconformity of Addresses of Items NA Information Directed to the Office of Nuclear Reactor Regulation GL 77-06 Questionnaire Related to Steam NA Applicable to licensed plants Generators GL 77-07 Reliability of Standby Diesel Generator NA Applicable to licensed plants Units GL 77-08 Revised Intrusion Detection Systems NA Information Handbook and Entry Control Systems Handbook GL 78-01 Correction To Letter Of 12/15/77 NA Information GL 78-02 Asymmetric Loads Background and Closed TVA will evaluate the reactor coolant system, including the steam Revised Request for Additional generators, using the guidance in SRP Section 3.9.5 as part of the Information design completion activities.

GL 78-03 Request for Information on Cavity Annulus NA Applicable to licensed plants Seal Ring GL 78-04 Steam Gen-rator Operatig Hist...y NA Applicable to licensed plants GL 78-05 Internal Distribution Of Correspondence - NA Information Asking For Comments On Mass Mailing System GL 78-06 This Generic Letter Was Never Issued NA GL 78-07 This Generic Letter Was Never Issued NA GL 78-08 Enclosing NUREG-0408 RE Mark I NA BWR Containments, And Granting Exemption From GDC 50 And Enclosing Sample Notice GL 78-09 Multiple Subsequent Actuations of Safety NA BWR Relief Valves Followino an Isolated Event Page 18 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-10 Guidance On Radiological Environmental NA Information Monitoring GL 78-11 Guidance on Spent Fuel Pool NA Information Modifications GL 78-12 Notice Of Meeting Regarding NA Information "Implementation of 10 CFR 73.55 Requirements And Status Of Research..."

GL 78-13 Forwarding of NUREG-0219 (Draft 2) NA Information GL 78-14 Transmittal Of Draft NUREG-0219 For NA Information Comment GL 78-15 Request for Information on Control of NA See GL 81-07 Heavy Loads Near Spent Fuel GL 78-16 Request For Information On Control Of NA Superseded by GL 78-17 Heavy Loads Near Spent Fuel Pools GL 78-17 Corrected Letter On Heavy Loads Over. NA Information Spent Fuel GL 78-18 Corrected Letter On Heavy Loads Over NA Duplicate of GL 78-17 Spent Fuel GL 78-19 Enclosing Sandia Report SAND 77-0777, NA Information "Barrier Technology Handbook" GL 78-20 Enclosing - "A Systematic Approach To NA Information The Conceptual Design Of Physical Protection Systems For Nuclear Facilities" GL 78-21 Transmitting NUREG/CR-0181 NA Information Concerning Barrier & Penetration Data Needed For Physical Security System Assessment GL 78-22 Revision To Intrusion Detection Systems NA Information And Entry Control Handbooks And Nuclear Safeguards Technology Handbook Page 19 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-23 Manpower Requirements For Operating NA Information Reactors GL 78-24 Model Appendix I Technical Specifications NA BWR And Submittal Schedule For BWRs GL 78-25 This Generic Letter Was Never Issued NA GL 78-26 Excessive Control Rod Guide Tube Wear Closed TVA will evaluate fuel-related component fretting using the guidance in SRP Section 4.2 as part of the design completion activities.

GL 78-27 Forwarding of NUREG-0181 NA Information GL 78-28 Forwarding pages omitted from 07/11/78 NA BWR letter GL 78-29 Notice of PWR steam generator NA Information conference GL 78-30 Forwarding of NUREG-0219 NA Information GL 78-31 Notice of Steam Generator Conference NA Information Agenda GL 78-32 Reactor Protection System Power NA BWR Supplies GL 78-33 Meeting Schedule And Locations For NA Information Upgraded Guard Qualification

• , -. I,-d'

,!A ,-,Lyv,*.0, Vw~USee Maer, 78-12 GL 78-35 Regional Meetings To Discuss Upgraded NA Information Guard Qualifications GL 78-36 Cessation of Plutonium Shipments By Air NA Does not apply to power reactor Except In NRC Approved Containers GL 78-37 Revised Meeting Schedule & Locations NA Information For Upgraded Guard Qualifications GL 78-38 Forwarding Of 2 Tables Of Appendix I, NA Applicable to licensed plants Draft Radiological Effluent Technical Specifications, PWR, and NUREG-0133 Page 20 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 78-39 Forwarding of 2 Tables of Appendix I, NA BWR Draft Radiological Effluent Technical Specifications, BWR, And NUREG-0133 GL 78-40 Training & Qualification Program NA Information Workshops GL 78-41 Mark II Generic Acceptance Criteria For NA BWR Lead Plants GL 78-42 Training and Qualification Program NA Information Workshops GL 79-01 Interservice Procedures for Instructional NA Information Systems Development - TRADOC GL 79-02 Transmitting Rev. to Entry Control NA Information Systems Handbook, Intrusion Detection Handbook, and Barrier Penetration Database GL 79-03 Offsite Dose Calculation Manual NA Information.

GL 79-04 Referencing 4/14/78 Letter - Modifications NA Information to NRC Guidance "Review and Acceptance 4

of Spent Fuel Pool Storage and H-nandling" GL 79-05 Information Relating to Categorization of NA Information Recent Regulatory Guides by the Regulatory Requirements Review Committee GL 79-06 Contents of the Offsite Dose Calculation NA Information Manual GL 79-07 Seismic (SSE) and LOCA Responses NA Information (NUREG-0484)

GL 79-08 Amendment to 10 CFR 73.55 NA Information Page 21 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-09 Staff Evaluation of Interim Multiple- NA BWR Consecutive Safety-Relief Valve Actuations GL 79-10 Transmitting Regulatory Guide 2.6 for NA Does not apply to power reactors Comment GL 79-11 Transmitting "Summary of Operating NA Information Experience with Recalculating Steam Generators, January 1979" NUREG-0523 GL 79-12 ATWS - Enclosing Letter to GE, with NA Information NUREG-0460, Vol. 3 GL 79-13 Schedule for Implementation and NA Information Resolution of Mark I Containment Long Term Program GL 79-14 Pipe Crack Study Group - Enclosing NA Information NUREG-0531 and Notice GL 79-15 Steam Generators-Enclosing Summary of NA Information Operating Experience with Recirculating Steam Generators, NUREG-0523 GL 79-16 Meeting Re Implementation Of Physical NA Information Sec, rity Requirements GL 79-17 Reliability of Onsite Diesel Generators at NA Information Light Water Reactors GL 79-18 Westinghouse Two-Loop NSSS NA Addressed to specific plants GL 79-19 NRC Staff Review of Responses to I&E NA Addressed to specific plants Bulletins 79-06 and 79-06a GL 79-20 Cracking in Feedwater Lines Closed See IEB 79-13.

GL 79-21 Enclosing NUREG/CR 0660, NA Information "Enhancement of on Site Emergency Diesel Generator Reliability" Page 22 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-22 Enclosing NUREG-0560, "Staff Report on NA Information the Generic Assessment of Feedwater Transients in PWRs Designed by B&W GL 79-23 NRC Staff Review of Responses to I&E NA BWR Bulletin 79-08 GL 79-24 Multiple Equipment.Failures in Safety NA Applicable to licensed plants Related Systems GL 79-25 Information Required to Review Corporate NA Information Capabilities GL 79-26 Upgraded Standard Technical NA Information Specification Bases Program GL 79-27 Operability Testing of Relief and Safety NA BWR Relief Valves GL 79-28 Evaluation of Semi-Scale Small Break NA Information Experiment GL 79-29 Transmitting NUREG-0473, Revision 2, NA Information Draft Radiological Effluent Technical Specifications GL 79-30 Transmitting NUREG-0472, Revision 2, NA Information Draft Radiological Techn~ical Spcfcain GL 79-31 Submittal of Copies of Response to NA Information 6/29/79 NRC Request GL 79-32 Transmitting NUREG-0578, "TMI-2 NA Information Lessons Learned" GL 79-33 Transmitting NUREG-0576 - Security NA Information Training and Qualification Plans GL 79-34 New Physical Security Plans (FR 43280- NA Does not apply to power reactors 285) 1 GL 79-35 Regional Meetings to Discuss Impacts on NA Information Emergency Planning I _

Page 23 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-36 Adequacy of Station Electric Distribution Closed TVA will evaluate the electric power system voltages using the Systems Voltages guidance in SRP Section 8.3.1 and BTP 8-6 as part of the design completion activities.

GL 79-37 Amendment to 10 CFR 73.55 Deferral NA Information from 8/1/79 to 11/1/79 GL 79-38 BWR Off-Gas Systems - Enclosing NA BWR NUREG/CR-0727 GL 79-39 Transmitting Division 5 Draft Regulatory NA Does not apply to power reactor Guide and Value Impact Statement GL 79-40 Follow-up Actions Resulting from the NRC NA Applicable to licensed plants Staff Reviews Regarding the TMI-2 Accident GL 79-41 Compliance with 40 CFR 190, EPA NA Information Uranium Fuel Cycle Standard GL 79-42 Potentially Unreviewed Safety Question on NA Applicable to licensed plants Interaction Between Non-Safety Grade Systems and Safety Grade Systems GL 79-43 Reactor Cavity Seal Ring Generic Issue NA Addressed to specific plants GL 79-44 Referencing 6/29/79 Letter Re Multiple NA Applicable to licensed plants Equipment Failures GL 79-45 Transmittal of Reports Regarding Foreign NA Information Reactor Operating Experiences GL 79-46 Containment Purge and Venting During Closed TVA will design the containment purge and vent valves using the Normal Operation guidance in SRP Section 6.2.4 as part of the design completion activities.

GL 79-47 Radiation Training NA Information GL 79-48 Confirmatory Requirements Relating to NA BWR Condensation Oscillation Loads for the Mark I Containment Long Term Program Page 24 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-49 Summary Of Meetings Held On NA Information September 18-20, .1979 To Discuss A Potential Unreviewed Safety Question On Interaction Between Non-Safety Grade Systems And NSSS Supplied Safety Grade Systems GL 79-50 Emergency Plans Submittal Dates NA Information GL 79-51 Follow-up Actions Resulting from the NRC NA Information Staff Reviews Regarding the TMI-2 Accident GL 79-52 Radioactive Release at No. Anna Unit 1 NA Applicable to licensed plants and Lessons Learned GL 79-53 ATWS NA Information GL 79-54 Containment Purging and Venting During NA Addressed to specific plants Normal Operation GL 79-55 Summary of Meeting Held on October 12, NA Information 1979 to Discuss Responses to IE Bulletins79-05C and 79-06C and HPI Termination Criteria GL. 79-56.... Discsion c of L arned £hnrt ,A Applicable to ,c.nse. pan'o*

Term Requirements GL 79-57 Acceptance Criteria for Mark I Long Term NA BWR Program GL 79-58 ECCS Calculations on Fuel Cladding NA Applicable to licensed plants GL 79-59 None NA GL 79-60 Discussion of Lessons Learned Short NA Information Term Requirements GL 79-61 Discussion of Lessons Learned Short NA Information Term Requirements GL 79-62 ECCS Calculations on Fuel Cladding NA Duplicate of GL 79-58.

Page 25 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 79-63 Upgraded Emergency Plans NA See TVA letter dated 7/29/08 for WBN2 GL 79-64 Suspension of All Operating Licenses NA Information GL 79-65 Radiological Environmental Monitoring NA Information Program Requirements - Enclosing Branch Technical Position, Revision 1 GL 79-66 Additional Information Re 11/09/79 Letter NA Information on ECCS Calculations GL 79-67 Estimates for Evacuation of Various Areas NA Information Around Nuclear Power Reactors GL 79-68 Audit of Small Break LOCA Guidelines NA Information GL 79-69 Cladding Rupture, Swelling, and Coolant NA Information Blockage as a Result of a Reactor Accident GL 79-70 Environmental Monitoring for Direct NA Information Radiation GL 80-01 NUREG-0630 "Cladding, Swelling And NA Information Rupture - Models For LOCA Analysis" GL 80-02 QA Requirements Regarding Diesel NA Information Generator Fuel Oil G- 03 BWR %ControlRod Failures BWR GL 80-04 IEB 80-01 Operability Of ADS Valve NA BWR Pneumatic Supply GL 80-05 IEB 79-01b Environmental Qualification Of NA Information Class 1E Equipment GL 80-06 Issuance Of Nureg-0313, Rev. 1, NA BWR "Technical Report On Material Selection And Processing Guidelines For Bwr Coolant Pressure Boundary Piping" Page 26 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-07 Information Regarding The Program For NA This GL was never issued.

Environmental Qualification Of Safety-Related Electrical Equipment GL 80-08 IEB 80-02 Inadequate Quality Assurance NA BWR For Nuclear Supplied Equipment GL 80-09 Low Level Radioactive Waste Disposal NA Applicable to licensed plants GL 80-10 Issuance Of NUREG-0588, "Interim Staff NA Information Position On Equipment Qualifications Of Safety-Related Electrical Equipment GL 80-11 IEB 80-03 Loss Of Charcoal From NA Information Standard Type II, 2 Inch, Tray Absorber Cells GL 80-12 IEB 80-04 Analysis Of A PWR Main Steam NA Information Line Break With Continued Feedwater Addition GL 80-13 Qualification of Safety Related Electrical NA Applicable to licensed plants Equipment GL 80-14 LWR Primary Coolant System Pressure Closed TVA will evaluate the valve configurations that connect high pressure Isolation Valves systems (Reactor Coolant System) to low pressure systems in light of the WASH 1400 Event V resuiis, and take appropriate design and/or Technical specification/administrative actions to minimize the core melt frequency associated with intersystem loss-of-coolant accidents as part of the plant completion activities.

GL 80-15 Request For Additional Management And NA Information Technical Resources Information GL 80-16 IEB 79-01b Environmental Qualification Of NA Information Class IE Equipment GL 80-17 Modifications To Boiling Water Reactor NA BWR Control Rod Drive Systems Page 27 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-18 Crystal River 3 Reactor Trip From Closed TVA will evaluate DC power system failure modes and effects using Approximately 100% Full Power the guidance of SRP Section 8.3.2 for DC system as part of the design completion activities.

GL 80-19 Resolution Of Enhanced Fission Gas NA Information Release Concern GL 80-20 Actions Required From OL Applicants Of NA Information NSSS Designs By W and CE Resulting From NRC B&O Task Force Review Of TMI2 Accident GL 80-21 Vacuum Condition Resulting in Damage to Closed See IEB 80-05.

Chemical Volume Control System Holdup Tanks GL 80-22 Transmittal Of NUREG-0654 "Criteria For NA Information Preparation And Evaluation Of Radiological Emergency Response Plans And Prepared GL 80-23 Change Of Submittal Date For Evaluation NA Information Time Estimates GL 80-24 Transmittal Of Information On NRC NA Information "Nuclear Data Link Specification,"

GL 80-25 IEB 80-06 Engineering Safety Feature NA Information (ESF) Reset Controls GL 80-26 Qualifications Of Reactor Operators NA Information GL 80-27 IEB 80-07 BWR Jet Pump Assembly NA BWR Failure GL 80-28 IEB 80-08 Examination Of Containment NA Information Liner Penetration Welds GL 80-29 Modifications To Boiling Water Reactor NA BWR Control Rod Drive Systems Page 28 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-30 Clarification Of The Term "Operable" As It NA Applicable to licensed plants Applies To Single Failure Criterion For Safety Systems Required By TS GL 80-31 IEB 80-09 Hydramotor Actuator NA Information Deficiencies GL 80-32 Information Request on Category I NA Addressed by IEB 80-11.

Masonry Walls Employed by Plants Under CP and OL Review GL 80-33 Actions Req. From OL Applicants Of B&W Closed TVA will design the Auxiliary Feedwater System using the guidance Designed NSSS Resulting From NRC of SRP Section 10.4.7. BTP 10-1, and TMI Item I1.E.1.1 as part of the B&O Task Force Review Of TMI2 Accident design completion activities.

GL 80-34 Clarification of NRC Requirements for NA Information Emergency Response Facilities at Each Site

• GL 80-35 Effect Of A DC Power Supply Failure On NA BWR ECCS Performances GL 80-36 THIS GENERIC LETTER IS A COVER NA Information LETTER FOR BULLETIN NO. 80-10 GL 80-37 Five Additional TMI-2 Related NA Applicable to licensed plants Requirements To Operatinrl P'tnrc GL 80-38 Summary of Certain Non-Power Reactor NA Does not apply to power reactors Physical Protection Requirements GL 80-39 IEB 80-11 Masonry Wall Design NA Information GL 80-40 Cover Letter for NUREGs-0645 & NA Information NUREG-0626 GL 80-41 Summary Of Meetings Held On April 22 NA Information

&23, 1980 With Representatives Of The Mark I Owners Group GL 80-42 IEB 80-12 Decay Heat Removal System NA Information Operability I I Page 29 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-43 IEB 80-13 Cracking In Core Spray NA BWR Spargers GL 80-44 Reorganization Of Functions And NA Information Assignments Within ONRR/SSPB GL 80-45 Fire Protection Rule NA Applicable to licensed plants GL 80- A-12, Fracture Toughness and Additional Closed No response was required for this GL. NUREG-0577 resolved the 46/47 Guidance on Potential for Low Fracture laminar tearing issue, and further stated that for plants under review Toughness and Laminar Tearing on PWR the fracture toughness issue was resolved.

Steam Generator Coolant Pump Supports GL 80-48 Revision To 5/19/80 Letter On Fire NA Applicable to licensed plants Protection GL 80-49 Nuclear Safeguards Problems NA Information GL 80-50 Generic Activity A-10 BWR Cracks NA BWR GL 80-51 On-Site Storage Of Low-Level Waste NA Applicable to licensed plants GL 80-52 Five Additional TMI-2 Related NA Applicable to licensed plants Requirements - Erata Sheets To 5/7/80 Letter GL 80-53 Decay Heat Removal Capability NA Applicable to licensed plants GL 80-54 IEB 80-14 Degradation Of Scram NA BWR

________Discharge Volume Capability I______________ I_______________________________

GL 80-55 IEB 80-15 Possible Loss Of Hotline With NA Information Loss Of Off-Site Power GL 80-56 Commission Memorandum And Order On NA Information Equipment Qualification GL 80-57 Further Commission Guidance For Power NA Information Reactor Operating Licenses NUREG-0660 And NUREG-0694 Page 30 of 61 TVA Letter dated October.10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-58 IEB 80-16 Potential Misapplication Of NA Information Rosemount Inc. Models 115111152 Pressure Transmitters With "A" Or "D" Output Codes GL 80-59 Transmittal Of Federal Register Notice RE NA Information Regional Meetings To Discuss Environmental Qualification Of Elec.

Equipment GL 80-60 Request for Information Regarding NA Information Evaluation Times GL 80-61 TMI-2 Lessons Learned NA Information GL 80-62 TMI-2 Lessons Learned NA BWR GL 80-63 IEB.80-17 Failure Of Control Rods To NA BWR Insert During A Scram At A BWR GL 80-64 Scram Discharge Volume Designs NA BWR GL 80-65 Request For Estimated Construction NA Information Completion And Fuel Load Schedules GL 80-66 IEB 80-17 Supplement 1 Failure Of NA BWR Control Rods To Insert During A Scram At A BWR GL 80-67 Scram Discharge Volume NA BWR GL 80-68 IEB 80-17 Supplement 2 Failures NA Information Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A GL 80-69 IEB 80-18 Maintenance Of Adequate NA Information Minimum Flow Through Centrifugal Charging Pumps Following Secondary I Side Helb Page 31 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GIL 80-70 IEB 80-19 Failures Of Mercury-Wetted NA Information Matrix Relays In RPS Of Operating Nuclear Power Plants Designed By GE GL 80-71 IEB 80-20 Failures Of Westinghouse Type NA Information W-2 Spring Return To Neutral Control Switches GL 80-72 Interim Criteria For Shift Staffing NA Information GL 80-73 "Functional Criteria For Emergency NA Information Response Facilities", NUREG-0696 GL 80-74 Forthcoming Meeting With NA Information Representatives Of The Electric Power Research Institute To Discuss Program For Resolution Of USI A-12 Fracture Toughness Issue GL 80-75 Lessons Learned Tech Specs NA Applicable to licensed plants GL 80-76 Notice Of Forthcoming Meeting With GE NA Information To Discussed Proposed BWR Feedwater Nozzle Leakage Detection System GL 80-77 Refueling Water Level - Technical NA Westinghouse plants only Specifications Changes GL 80-78 Mark I Containment Long-Term Program NA BWR GL 80-79 This generic letter is a cover letter for NA Information bulletin no. 80-17, supplement 3 GL 80-80 Preliminary Clarification Of TMI Action NA Information Plan Requirements GL 80-81 Preliminary Clarification Of TMI Action NA Information Plan Requirements - Addendum To 9/5/80 Letter GL 80-82 IEB 79-01b Supplement 2 Environmental NA Information Qualification Of Class 1E Equipment Page 32 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-83 Environmental Qualification Of Safety- NA Information Related Equipment GL 80-84 BWR Scram System NA BWR GL 80-85 Implementation of Guidance From NA Information Unresolved Safety Issue A-12, "Potential For Low Fracture Toughness and Lamellar Tearing on Component Supports" GL 80-86 Notice Of Meeting To Discuss Final NA Information Resolution Of USI A-12 GL 80-87 Notice Of Meeting To Discuss Status Of NA Information EPRI-Proposed Resolution Of The USI A-12 Fracture Toughness Issue GL 80-88 Seismic Qualification Of Auxiliary NA Applicable to licensed plants Feedwater Systems GL 80-89 IEB 79-01 b Supplement 3 Environmental NA Information Qualification Of Class 1E Equipment GL 80-90 NUREG-0737, TMI (Prior and future GLs, Closed The requirements of Supplement 1 to NUREG 0737 are addressed in with the exception of certain discrete the applicable TMI Items referenced in Table 1.

scopes, have been screened into the NUREG 0737Hst foritems applicable to BLN)

GL 80-91 Odyn Code Calculation NA BWR GL 80-92 IEB 80-21 Valve Yokes Supplied By NA Information Malcolm Foundry Company, Inc.

GL 80-93 Emergency Preparedness NA Does not apply to power reactors GL 80-94 Emergency Plan NA Information GL 80-95 A-10, NUREG-0619, "BWR Feedwater NA BWR Nozzle and Control Rod Drive Return Line Cracking" GL 80-96 Fire Protection NA Addressed to specific plants Page 33.of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 80-97 IEB 80-23 Failures Of Solenoid Valves NA Information Manufactured By Valcor Engineering Corporation GL 80-98 IEB 80-24 Prevention Of Damage Due To NA Information Water Leakage Inside Containment GL 80-99 Technical Specification Revisions For NA Information Snubber Surveillance GL 80-100 Appendix R to 10 CFR 50 Regarding Fire NA Applicable to licensed plants Protection-Federal Register Notice GL 80-101 Inservice Inspection Programs NA Addressed to specific plants.

GL 80-102 Commission Memorandum And Order Of NA Information May 23, 1980 GL 80-103 Fire Protection - Revised Federal Register NA Information Notice GL 80-104 Orders On Environmental Qualification Of NA Information Safety Related Electrical Equipment GL 80-105 Implementation Of Guidance For USI A- NA Information 12, Potential For Low Fracture Toughness And Lamellar Tearing On Component Supports GL 80-106 Report On ECCS Cladding Models, NA Information NUREG-0630 GL 80-107 BWR Scram Discharge System NA BWR GL 80-108 Emergency Planning NA Information GL 80-109 Guidelines For SEP Soil Structure NA Information Interaction Reviews GL 80-110 Periodic Updating Of FSARS NA Applicable to licensed plants GL 80-111 IEB 80-17 Supplement 4, Failure Of NA BWR Control Rods To Insert During A Scram At A BWR Page 34 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item _BLN Title Status TVA Action to be Completed or Justification for Closure GL 80-112 IEB 80-25 Operating Problems With NA Information Target Rock Safety Relief Valves GL 80-113 Control of Heavy Loads Closed Superseded by GL 81-07 GL 81-01 Qualification of Inspection, Examination, NA Information Testing and Audit Personnel GL 81-02 Analysis, Conclusions and NA Information Recommendations Concerning Operator Licensing GL 81-03 NUREG-0313, Technical Report on NA BWR Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping GL 81-04 Emergency Procedures and Training for Closed Subsumed by Station Blackout Station Blackout GL 81-05 Information Regarding The Program For Closed This GL is addressed by the BLN EQ Program, which will meet the Environmental Qualification Of Safety- requirements of 10 CFR 50.49 using the guidance of SRP Section Related Electrical Equipment 3.11 as part of the design competition activities.

GL 81-06 Periodic Updating of Final Safety Analysis NA Information Reports (FSARS)

GL 81-07 Control a' Ieavy 1 Loads Ciosed TVA will ensure that plant design satisfies the guidance in SRP Section 9.1.5 and NUREG-0612 as part of the design completion activities.

GL 81-08 Odyn Code NA BWR GL 81-09 BWR Scram Discharge System NA BWR GL 81-10 Post-TMI Requirements For The NA Information Emergency Operations Facility GL 81-11 BWR Feedwater Nozzle and Control Rod NA BWR Drive Return Line Nozzle Cracking (NUREG-0619)

GL 81-12 Fire Protection Rule (and prior related NA Applicable to licensed plants GLs)

Page 35 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 81-13 SER For GEXL Correlation For 8X8R Fuel NA BWR Reload Applications For Appendix D Submittals of The GE Topical Report GL 81-14 Seismic Qualification of Auxiliary Closed TVA will address the applicable BLN design requirements for the Feedwater Systems Auxiliary Feedwater system using the guidance in SRP Section 10.4.9 as part of the design completion activities.

GL 81-15 Environmental Qualification of Class 1E NA Information Electrical Equipment-Clarification of Staffs Handling of Proprietary Information GL 81-16 NUREG-0737 Item I.C.1 SER on NA See NUREG list in this table Abnormal Transient Operating Guidelines (ATOG)

GL 81-17 Functional Criteria for Emergency NA Information Response Facilities GL 81-18 BWR Scram Discharge System- NA BWR Clarification of Diverse Instrumentation Requirements GL 81-19 Thermal Shock to Reactor Pressure NA Applicable to licensed plants Vessels r,-i %M..9n l SConcerns zf " r, Associated With Pipe ~

AI+,D,,

NABWR [31A,;f,-

Breaks in The BWR Scram System GL 81-21 Natural Circulation Cooldown Closed TVA will develop procedures to address natural circulation capability using the guidance of SRP Section 13.5.2.1 as part of the plant completion activities.

GL 81-22 Engineering Evaluation of The H.B. NA Information Robinson Reactor Coolant System Leak on 1/29/81 GL 81-23 INPO Plant Specific Evaluation Reports NA Information GL 81-24 Multi-Plant Issue B-56 Control Rods Fail NA BWR To Fully Insert Page 36 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 81-25 Change in Implementing Schedule For NA Information Submission and Evaluation of Upgraded Emergency Plans GL 81-26 Licensing Requirements for Pending NA Addressed to applicants with pending construction permits Construction Permit and Manufacturing License Applications GL 81-27 Privacy and Proprietary Material in NA Information Emergency Plans GL 81-28 Steam Generator Overfill NA Information GL 81-29 Simulator Examinations NA Information GL 81-30 Safety Concerns Associated With Pipe NA BWR Breaks in the BWR Scram System GL 81-31 Small Break LOCA Confirmatory Integral NA This GL was never issued.

Systems Experiments for B&W Designed Plants_

GL 81-32 NUREG-0737, Item II.K.3.44-Evaluation of NA BWR Anticipated Transients Combined With Single Failure GL 81-33 Technical Specification for Station NA This GL was never issued Batteries Multi-plant Action GL 81-34 & Safety Concerns Associated With Pipe NA BWR

-35 Breaks in the BWR Scram System GL 81-36 Revised Schedule for Completion of TMI NA Information Action Plan Item ll.D.1, Relief and Safety Valve Testing GL 81-37 ODYN Code Reanalysis Requirements NA BWR GL 81-38 Storage of Low Level Radioactive Wastes NA Information at Power Reactor Sites GL 81-39 NRC Volume Reduction Policy NA Information GL 81-40 Qualifications of Reactor Operators NA Information Page 37 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 82-01 New Applications Survey NA Information GL 82-02 Commission Policy on Overtime NA Information GL 82-03 High Burnup MAPLHGR Limits NA BWR GL 82-04 Use of INPO See-in Program NA Information GL 82-05 Post-TMI Requirements NA Applicable to licensed plants GL 82-06 This Generic Letter Was Never Issued NA GL 82-07 Transmittal of NUREG-0909 Relative to NA Information the Ginna Tube Rupture GL 82-08 Transmittal of NUREG-0909 Relative to NA Information the Ginna Tube Rupture GL 82-09 Environmental Qualification of Safety Closed This GL is addressed by the BLN EQ Program, which will meet the Related Electrical Equipment requirements of 10 CFR 50.49 using the guidance of SRP Section 3.11 as part of the design competition activities..

GL 82-10 Post-TMI Requirements NA Applicable to licensed plants GL 82-11 Transmittal of NUREG-0916 Relative to NA Information the Restart of R.E. Ginna Nuclear Power Plant GL 82-12 Nuclear Power Plant Staff Working Hours NA Information GL 82-13 Reactor Operator and Senior Reactor NA Information Operator Examinations GL 82-14 Submittal of Documents to the NRC NA Information GL 82-15 This Generic Letter Was Never Issued NA GL 82-16 NUREG-0737 Technical Specifications NA Applicable to licensed plants GL 82-17 Inconsistency of Requirements Between NA Information 50.54(t) and 50.15 GL 82-18 Reactor Operator and Senior Reactor NA Information Operator Requalification Examinations GL 82-19 Submittal of Copies of Documentation to NA Information NRC-Copy Requirements for Emergency Plans and Physical Security Plans Page 38 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title ] BLN Status TVA Action to be Completed or Justification for Closure GL 82-20 Guidance for Implementing the Standard NA Information Review Plan Rule GL 82-21 Fire Protection Audits NA Information GL 82-22 Congressional Request for Information NA Applicable to licensed plants Concerning Steam Generator Tube Integrity GL 82-23 Inconsistency Between Requirements Of NA Information 10 CFR 73.40(d) And Standard Technical Specifications For Performing Audits Of Safeguards Contingency Plans GL 82-24 Safety Relief Valve Quencher Loads: NA BWR BWR MARK IIand III Containments GL 82-25 Integrated IAEA Exercise for Physical NA Applicable to licensed plants Inventory at LWRS GL 82-26 NUREG-0744, REV. 1 - Pressure Vessel NA Applicable to licensed plants Material Fracture Toughness GL 82-27 Transmittal of NUREG-0763 - Guidelines NA BWR For Confirmatory In-Plant Tests of Safety-Relief Valve Discharge for BWR Plants GL 82-28* inadequate Core Cooling Instrumentation Closed The Beliefonte design will implement the guidance from SRP Section System 7.5, BTP 7-10, and RG 1.97 R3 GL 82-29 This Generic Letter Was Never Issued NA This GL was never issued GL 82-30 Filings Related to 10 CFR 50 Production NA Information and Utilization Facilities GL 82-31 This Generic Letter Was Never Issued NA This GL was never issued GL 82-32 Draft Steam Generator Report (SAI) NA Applicable to licensed plants GL 82-33 Supplement to NUREG-0737, Closed The requirements of Supplement 1 to NUREG 0737 are addressed in Requirements for Emergency Response the applicable TMI Items referenced in Table 1.

Capability GL 82-34 This Generic Letter Was Never Issued NA Page 39 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 82-35 This Generic Letter Was Never Issued NA GL 82-36 This Generic Letter Was Never Issued NA GL 82-37 This Generic Letter Was Never Issued NA GL 82-38 Meeting to Discuss Developments for NA Information Operator Licensing Examinations GL 82-39 Problems With Submittals of Subsequent NA Information Information of CURT 73.21 For Licensing Reviews GL 83-01 Operator Licensing Examination Site Visit NA Information GL 83-02 NUREG-0737 Technical Specifications NA BWR GL 83-03 This GL was never used NA GL 83-04 Regional Workshops Regarding NA Information Supplement 1 to NUREG-0737, Requirements For Emergency Response Capability GL 83-05 Safety Evaluation of "Emergency NA BWR Procedure Guidelines, Revision 2," June 1982 GL 83-06 Certificates and Revised Format For NA Information.

Reactor Operator and Senior Reactor Operator Licenses GL 83-07 The Nuclear Waste Policy Act of 1982 NA Information GL 83-08 Modification of Vacuum Breakers on Mark NA BWR I Containments GL 83-09 Review of Combustion Engineering NA Applies only to CE designed plants Owners' Group Emergency Procedures Guideline Program GL 83-10a, Resolution of TMI Action Item I1.K.3.5 NA Applicable only to Westinghouse and CE plants b, c, & d "Automatic Trip of Reactor Coolant Pumps" Page 40 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 83-10e Resolution of TMI Action Item II.K.3.5 Closed See TMI Item II.K.3.5 referenced in SRP 15.6.5 of Table 1.

&f "Automatic Trip of Reactor Coolant Pumps" GL 83-11 Licensee Qualification for Performing NA Applicable to licensed plants Safety Analyses in Support of Licensing Actions GL 83-12 Issuance of NRC FORM 398 - Personal NA Information Qualifications Statement - Licensee GL 83-13 Clarification of Surveillance Requirements Closed TVA will use the NUREG-1430 B&W STS for the development of the for HEPA Filters and Charcoal Absorber BLN Technical Specifications and RG 1.52 for the development of Units In STD. Tech Specs on ESF the Ventilation Filter Testing Program.

Cleanup Systems GL 83-14 Definition of "Key Maintenance NA Information Personnel," (Clarification of Generic Letter 82-12)

GL 83-15 Implement. of Reg. Guide 1.150, NA Information "Ultrasonic Testing of RX Vessel Welds During Preservice & Inservice Examinations, Rev.1 GL 83-16 Transmittal of NUREG-0977 Relative to NA Information the ATWS Events at Salem Generating Station, Unit NO. 1 GL 83-17 Integrity of Requalification Examinations NA Information for Renewal of Reactor Operator and Senior Reactor Operator Licenses GL 83-18 NRC Staff Review of the BWR Owners' NA BWR Group (BWROG) Control Room Survey Program Page 41 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 83-19 New Procedures for Providing Public NA Applicable to licensed plants Notice Concerning Issuance of Amendments To Operating Licenses GL 83-20 Integrated Scheduling for Implementation NA Information of Plant Modifications GL 83-21 Clarification of Access Control Procedures NA Information for Law Enforcement Visits GL 83-22 Safety Evaluation of "Emergency NA Applies to Westinghouse PWRs only Response Guidelines" GL 83-23 Safety Evaluation of "Emergency NA Applies to CE PWRs only Procedure Guidelines" GL 83-24 TMI Task Action Plan Item I.G.1, "Special NA BWR Low Power Testing and Training,"

Recommendations for BWRs GL 83-25 This GL was. never issued NA GL 83-26 Clarification Of Surveillance Requirements NA Information For Diesel Fuel Impurity Level Tests GL 83-27 Surveillance Intervals in Standard NA Information Technical Specifications GL 83-28* Required Actions Based on Generic Closed TVA will incorporate the lessons learned from the Salem ATWS Implications of Salem ATWS Events: event into the RPS design using the guidance in SRP Section 7.2 as 1.2 - Post Trip Review Data and part of the design completion activities.

Information Capability As required by 10CFR50.62, TVA will provide the capability to 2.1 - Equipment Classification and Vendor automatically initiate the AFW system and initiate a turbine trip under Interface (Reactor Trip System conditions indicative of an ATWS with equipment from sensor output Components) to final actuation device diverse from the reactor trip system, will be 2.2 - Equipment Classification and Vendor met by incorporating ATWS mitigating system actuation circuitry Page 42 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure Interface (All SR Components) (AMSAC). In addition, a diverse scram system, from the sensor 3.1 - Post-Maintenance Testing (Reactor output to interruption of power to the control rods, will be provided by Trip System Components) the Diverse Scram System (DSS). These activities will be completed 3.2 - Post-Maintenance Testing (All SR as part of the design completion activities.

Components) 4.1 - Reactor Trip System Reliability (Vendor Related Modifications) 4.3 - Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment)

GL 83-29 This Generic Communication was not NA issued GL 83-30 Deletion of STD. Tech Spec Surveillance NA Information Requirement 4.8.1.1.2.d.6 For Diesel Generator Testing GL 83-31 Safety Evaluation of "Abnormal Transient NA Information.

Operating Guidelines" GL 83-32 NRC Staff Recommendations Regarding NA Information Operator Action for Reactor Trip and ATWS GL 83-33 NRC Positions on Certain Requirements NA Information of Appendix R to 10 CFR 50 GL 83-34 GL was never issued NA GL 83-35 Clarification of TMI Action Plan Item NA Information II.K.3.31 GL 83-36 NUREG-0737 Technical Specifications NA BWR GL 83-37 NUREG-0737 Technical Specifications NA Applicable to licensed plants GL 83-38 NUREG-0965, "NRC Inventory of Dams" NA Information GL 83-39 Voluntary Survey of Licensed Operators NA Information GL 83-40 Operator Licensing Examination NA Information Page 43 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 83-41 Fast Cold Starts of Diesel Generators NA Applicable to licensed plants.

GL 83-42 Clarification to GL 81-07 Regarding NA Information Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" GL 83-43 Reporting Requirements of 10 CFR 50, NA Information Sections 50.72 and 50.73, and Standard Technical Specifications GL 83-44 Availability of NUREG-1021, "Operator NA Information Licensing Examiner Standards" GL 84-01 NRC Use Of The Terms "Important To NA Information Safety" and "Safety Related" GL 84-02 Notice of Meeting Regarding Facility NA Information Staffing GL 84-03 Availability of NUREG-0933, "A NA Information Prioritization of Generic Safety Issues" GL 84-04 Safety Evaluation of Westinghouse NA Information Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)

CL184-05 Change to NUREG-1021, "Operator N,1A noatn Licensing Examiner Standards" GL 84-06 Operator and Senior Operator License NA Does not apply to power reactor Examination Criteria for Passing Grade GL 84-07 Procedural Guidance for Pipe NA BWR Replacement at BWRs GL 84-08 Interim Procedures for NRC Management NA Information of Plant-Specific Backfitting GL 84-09 Recombiner Capability Requirements of NA BWR 10 CFR 50.44(c)(3)(ii)

GL 84-10 Administration of Operating Tests Prior to NA Information Initial Criticality Page 44 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 84-11 Inspection of BWR Stainless Steel Piping NA BWR GL 84-12 Compliance W 10CFR61 and NA Information Implementation of Rad Effluent Tech Specs, Attendant Process Control Program GL 84-13 Technical Specification for Snubbers NA Information GL 84-14 Replacement and Requalification Training NA Information Program GL 84-15 Proposed Staff Actions to Improve and NA Information Maintain Diesel Generator Reliability GL 84-16 Adequacy of On-Shift Operating NA Information Experience for Near Term Operating License Applicants GL 84-17 Annual Meeting to Discuss Recent NA Information Developments Regarding Operator Training, Qualifications, and Examinations GL 84-18 Filing of Applications for Licenses and NA Does not apply to power reactors Amendments GL 84-19 Availability of Supplement 1 to NUREG- NA Information Issues" GL 84-20 Scheduling Guidance for Licensee NA Information Submittals of Reloads That Involve Unreviewed Safety Questions GL 84-21 Long Term Low Power Operation in NA Information Pressurized Water Reactors GL 84-22 GL was never issued NA GL 84-23 Reactor Vessel Water Level NA BWR Instrumentation in BWRs GL 84-24 Certification of Compliance to 10 CFR NA Implementation of the EQ Program will address 10 CFR 50.49 50.49 requirements.

Page 45 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 85-01 Fire Protection Policy Steering Committee NA Issued as draft Report GL 85-02 Recommended Actions Stemming From Closed TVA will implement a Steam Generator Program, as specified in NRC Integrated Program for the NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 Resolution of Unresolved Safety Issues as part of the plant completion activities.

Regarding Steam Generator Tube Integrity GL 85-03 Clarification of Equivalent Control Capacity NA BWR for Standby Liquid Control Systems GL 85-04 Operating Licensing Examinations NA Information.

GL 85-05 Inadvertent Boron Dilution Events NA Applicable to licensed plants GL 85-06 Quality Assurance Guidance for ATWS NA Information Equipment That Is Not Safety-Related GL 85-07 Implementation of Integrated Schedules NA Applicable to licensed plants for Plant Modifications GL 85-08 10 CFR 20.408 Termination Reports - NA Information Format GL 85-09 Technical Specifications For Generic NA Information Letter 83-28, Item 4.3 GL 85-10 Technical Specification For Generic Letter Closed TVA will implement the surveillance requirements for the reactor trip 83-28, Items 4.3 and 4.4 breakers, as specified in NUREG-1430 B&W STS as part of the plant completion activities.

GL 85-11 Completion of Phase II of "Control of Closed See GL 81-07 Heavy Loads at Nuclear Power Plants" GL 85-12 Implementation of TMI Item II.K.3.5 NA Applicable to Westinghouse plants only GL 85-13 Transmittal Of NUREG-1154 Regarding NA Information The Davis-Besse Loss Of Main And Auxiliary Feedwater Event GL 85-14 Commercial Storage At Power Reactor NA Applicable to licensed plants Sites Of Low Level Radioactive Waste Not Generated By The Utility Page 46 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 85-15 Information On Deadlines For NA Applicable to licensed plants 10CFR50.49, "EQ Of Electric Equipment Important To Safety At NPPS" GL 85-16 High Boron Concentrations NA Information GL 85-17 Availability Of Supplements 2 and 3 To NA Information NUREG-0933, "A Prioritization Of Generic Safety Issues" GL 85-18 Operator Licensing Examinations NA Information GL 85-19 Reporting Requirements On Primary NA Information Coolant Iodine Spikes GL 85-20 Resolution Of Generic Issue 69: High Closed TVA will implement the in-service inspection requirements of the Pressure Injection/Make-up Nozzle ASME Code as required by 10 CFR 50.55a using the guidance in Cracking In Babcock And Wilcox Plants SRP Section 5.2.4 as part of the plant completion activities.

GL 85-21 This Generic Communication was not NA issued GL 85-22 Potential For Loss Of Post-LOCA NA Information Recirculation Capability Due To Insulation Debris Blockage GL 86-01 Safety Concerns Associated With Pipe NA BWR Breaks in The BWR Scram System GL 86-02 Technical Resolution of Generic Issue B- NA BWR 19 - Thermal Hydraulic Stability GL 86-03 Applications For License Amendments NA Information GL 86-04 Policy Statement On Engineering NA Information Expertise On Shift GL 86-05 Implementation of TMI Item Il.K.3.5 Closed See response to TMI Item I.K.3.5 referenced in SRP 15.6.5 of Table 1.

GL 86-06 Implementation of TMI Item II.K.3.5 NA CE plants only Page 47 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 86-07 Transmittal of NUREG-1 190 Regarding NA Information The San Onofre Unit 1 Loss of Power And Water Hammer Event GL 86-08 Availability of Supplement 4 to NUREG- NA Information 0933, "A Prioritization of Generic Safety Issues" GL 86-09 Technical Resolution of Generic Issue B- NA Information 59, (n-i) Loop Operation in BWRs and PWRs GL 86-10 Implementation of Fire Protection NA Information Requirements GL 86-11 Distribution of Products Irradiated in NA Does not apply to power reactors Research Reactors GL 86-12 Criteria for Unique Purpose Exemption NA Does not apply to power reactors From Conversion From The Use of HEU Fuel GL 86-13 Potential Inconsistency Between Plant Closed The Bellefonte Technical Specifications will be developed based on Safety Analyses and Technical the plant safety analyses as part of the plant completion activities.

Specifications 86-14AL Operator Licensing E  ; I^ -A..rion GL 86-15 Information Relating To Compliance With NA Information 10 CFR 50.49, "Environmental Qualification Of Electric Equipment Important To Safety For Nuclear Power Plants", (Generic Letter 86-15)

GL 86-16 Westinghouse ECCS Evaluation Models NA Information GL 86-17 Availability of NU REG-1169, "Technical NA BWR Findings Related to Generic Issue C-8, BWR MSIC Leakage And Treatment Methods" Page 48 of 61

Enclosure I TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 87-01 Public Availability Of The NRC Operator NA Information Licensing Examination Question Bank GL 87-02 & Verification of Seismic Adequacy of NA Applicable to licensed plants 03 Mechanical and Electrical Equipment in Operating Reactors, USI A-46 GL 87-04 Temporary Exemption From Provisions Of NA Applicable to licensed plants The FBI Criminal History Rule For Temporary Workers GL 87-05 Request for Additional Information on NA BWR Assessment of License Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells GL 87-06 Periodic Verification of Leak Tight Integrity NA Applicable to licensed plants of Pressure Isolation Valves GL 87-07 Information Transmittal of Final NA Information Rulemaking For Revisions To Operator Licensing - 10 CFR 55 And Confirming Amendments GL 87-08 Implementation of 10 CFR 73.55 NA Applicable to licensed plants Miscellaneous Amendments and Search Requirements GL 87-09 Sections 3.0 And 4.0 of Standard Tech NA Information Specs on Limiting Conditions For Operation And Surveillance Requirements GL 87-10 Implementation of 10 CFR 73.57, NA Applicable to licensed plants Requirements For FBI Criminal History Checks GL 87-11 Relaxation in Arbitrary Intermediate Pipe NA Information Rupture Requirements GL 87-12 Loss of Residual Heat Removal While The Closed Superseded by GL 88-17 Reactor Coolant System is Partially Filled Page 49 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 87-13 Integrity of Requalification Examinations NA Does not apply to power reactors At Non-Power Reactors GL 87-14 Operator Licensing Examinations NA Information GL 87-15 Policy Statement On Deferred Plants NA Information GL 87-16 Transmittal of NUREG-1262, "Answers To NA Information Questions On Implementation Of 10 CFR 55 On Operators' Licenses" GL 88-01 NRC Position on IGSCC in BWR NA BWR Austenitic Stainless Steel Piping GL 88-02 Integrated Safety Assessment Program II NA Applicable to licensed plants (ISAP II)

GL 88-03 Resolution of GSI 93, Steam Binding of Closed See IEB 85-01.

Auxiliary Feedwater Pumps GL 88-04 Distribution of Gems Irradiated in NA Does not apply to power reactors Research Reactors GL 88-05* Boric Acid Corrosion of Carbon Steel Closed TVA will implement a boric acid corrosion program based on the Reactor Pressure Boundary Components vulnerabilities identified using the guidance of SRP Section 3.13 as in PWR plants part of the plant completion activities.

GL 88-06 Removal of Organization Charts from NA Information Technical Specification Administrative Control Requirements GL 88-07 Modified Enforcement Policy Relating to NA This GL deals with enforcement policy and TVA understands that 10 CFR 50.49, EQ of Electrical Equipment those policies apply to BLN.

Important to Safety for Nuclear Power Plants GL 88-08 Mail Sent or Delivered to the Office of NA Information Nuclear Reactor Regulation GL 88-09 Pilot Testing of Fundamentals NA BWR Examination GL 88-10 Purchase of GSA Approved Security NA Information Containers Page 50 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I &2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 88-11 NRC Position on Radiation Embrittlement Closed TVA will ensure that embrittlement effects are evaluated using the of Reactor Vessel Material and its Impact guidance of SRP Section 5.3.1 and RG 1.99 R2 as part of the design on Plant Operations completion activities.

GL 88-12 Removal of Fire Protection Requirements NA Information from Technical Specification GL 88-13 Operator Licensing Examinations NA Information GL 88-14* Instrument Air Supply System Problems Closed TVA will design the compressed air system using the guidance of Affecting Safety-Related Equipment SRP Section 9.3.1 as part of the design competition activities.

GL 88-15 Electric Power Systems - Inadequate NA Information Control Over Design Process GL 88-16 Removal of Cycle-Specific Parameter NA Information Limits from Technical Specifications GL 88-17* Loss of Decay Heat Removal Closed TVA will design the decay heat removal system using the guidance of SRP Section 5.4.7 as part of the design competition activities.

GL 88-18* Plant Record Storage on Optical Disks Closed Information. Additionally, in a letter dated 10/23/97, TVA provided NRC with its plans for control of plant record storage on optical disks.

GL 88-19 Use of Deadly Force by Licensee Guards Closed TVA will implement a physical security plan as required by 10 CFR to Prevent Theft of Special Nuclear 73.55 and using the guidance in SRP 13.6.1 as part of the plant Material completion activities.

GL 88-20" Individual Plant Examination-or Severe Closed WVA wiii develop a piant-specific PRA for BLN using the guidance of Accident Vulnerability SRP Section 19.1 as part of the design completion activities.

GL 89-01 Implementation of Programmatic and NA Information Procedural Controls for Radiological Effluent Technical Specifications GL 89-02 Actions to Improve the Detection of NA Information Counterfeit and Fraudulently Marketed Products GL 89-03 Operator Licensing Examination Schedule NA Information GL 89-04* Guidelines on Developing Acceptable Closed TVA will implement the in-service testing requirements of the ASME Inservice Testing Programs Code as required by 10 CFR 50.55a in accordance with NUREG-1430 B&W STS as part of the plant completion activities.

Page 51 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 89-05 Pilot Testing of the Fundamentals NA Information Examination GL 89-06 TMI Action Plan Item I.D.2 - Safety Closed See response to TMI Item I.D.2 referenced in SRP 18.0 in Table 1.

Parameter Display System GL 89-07 Power Reactor Safeguards Contingency Closed TVA will implement a physical security plan as required by 10 CFR Planning for Surface Vehicle Bombs 73.55 and using the guidance in SRP 13.6.1 as part of the plant completion activities.

GL 89-08* Erosion/Corrosion-Induced Pipe Wall Closed TVA will implement a flow accelerated corrosion program using the Thinning guidance of SRP Section 10.4.7 as part of the plant completion activities.

GL 89-09 ASME Section III Component NA Applicable to licensed plants Replacements GL 89-10* Safety-Related Motor-Operated Valve Closed TVA will implement a Motor-Operated Valve Testing program using Testing and Surveillance the guidance of SRP Section 3.9.6 as part of the plant completion activities.

GL 89-11 Resolution of Generic Issue 101 "Boiling NA BWR Water Reactor Water Level Redundancy" GL 89-12 Operator Licensing Examination NA Information.

GL 89-13" Service Water System Problems Affecting Closed TVA will implement a service water monitoring program using the Safety Related Equipment guidance of SRP Section . 4. as part of the plant completion activities.

GL 89-14 Line-Item Improvements in Technical NA Information Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals GL 89-15 Emergency Response Data System NA Information GL 89-16 Installation of a Hardened Wetwell Vent NA BWR GL 89-17 Planned Administrative Changes to the NA Information NRC Operator Licensing Written Examination Process Page 52 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 89-18 Resolution of Unresolved Safety Issues A- NA Information 17, "Systems Interactions in Nuclear Power Plants" GL 89-19 Request for Actions Related to Resolution Closed TVA will use the guidance in SRP Section 7.3 to incorporate of Unresolved Safety Issue A-47 "Safety automatic steam generator overfill protection as part of the design Implication of Control Systems in LWR completion activities.

Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)

GL 89-20 Protected Area Long Term Housekeeping NA Does not apply to power reactors GL 89-21 Request for Information Concerning Status Closed See USI Section of this submittal (Table 3).

of Implementation of Unresolved Safety Issue (USI) Requirements GL 89-22 Potential For Increased Roof Load Due to NA No response required.

Changes in Maximum Precipitation GL 89-23 NRC Staff Responses to Questions NA Information Pertaining to Implementation of 10 CFR Part 26 GL 90-01 Request for Voluntary Participation in NRC NA Information Regulatory Impact Survey G1 90-02 Alternative Requ,;ments for Fuel KIA Info.matio Assemblies in the Design Features Section of Technical Specifications GL 90-03 Relaxation of Staff Position in Generic NA Information Letter 83-28, Item 2.2 Part 2 "Vendor Interface for Safety-Related Components" GL 90-04 Request for Information on the Status of Closed See USI Section of this submittal (Table 3).

Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs Page 53 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 90-05 Guidance for Performing Temporary Non- NA Information Code Repair of ASME Code Class 1, 2, and 3 Piping GL 90-06* Resolution of Generic Issues 70, "PORV Closed TVA will address the PORV requirements using the guidance of SRP and Block Valve Reliability," and 94, Section 5.2.2 and NUREG-1430 B&W STS as part of the design "Additional LTOP Protection for PWRs" completion activities.

GL 90-07 Operator Licensing National Examination NA Information Schedule GL 90-08 Simulation Facility Exemptions NA Information GL 90-09 Alternative Requirements for Snubber NA Information Visual Inspection Intervals and Corrective Actions GL 91-01 Removal of the Schedule for the NA Information Withdrawal of Reactor Vessel Material Specimens from Technical Specifications GL 91-02 Reporting Mishaps Involving LLW Forms NA Applicable to licensed plants Prepared for Disposal GL 91-03 Reporting of Safeguards Events NA Information GL 91-04 Changes in Technical Specification NA Information

-UnlaVItld I It iuVadl Lu Accommodate a 24-Mo'nth Fuel Cycle GL 91-05 Licensee Commercial-Grade Procurement NA Information and Dedication Programs GL 91-06 Resolution of Generic Issue A-30, NA Applicable to licensed plants "Adequacy of Safety Related DC Power Supplies" GL 91-07 GI-23, "Reactor Coolant Pump Seal NA Information Failures" and Its Possible Effect on Station Blackout GL 91-08 Removal of Component Lists from NA Information Technical Specifications I Page 54 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 91-09 Modification of Surveillance Interval for the NA Information Electrical Protective Assemblies in Power Supplies for the Reactor Protection System GL 91-10 Explosives Searches at Protected Area NA Does not apply to power reactors Portals GL 91-11 Resolution of Generic Issues A-48, "LCOs NA Applicable to licensed plants for Class 1 E Vital Instrument Buses", and 49, "Interlocks and LCOs for 1E Tie Breakers" GL 91-12 Operator Licensing National Examination NA Information Schedule GL 91-13 Request for Information Related to NA Addressed to specific plants Resolution of Generic Issue 130, "Essential Service Water System Failures

@cMulti-Unit Sites" GL 91-14 Emergency Telecommunications NA Information GL 91-15 Operating Experience Feedback Report, NA Information Solenoid-Operated Valve Problems at U.S. Reactors GL 91-16 Licensed Operators' and Other Nuclear NA Information Facility Personnel Fitness for Duty GL 91-17 Generic Safety Issue 29, "Bolting NA Information Degradation or Failure in Nuclear Power Plants" GL 91-18 Information to Licensees Regarding Two NA GL 91-18 has been superseded by RIS 2005-20 NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability]

Page 55 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 91-19 Information to Addressees Regarding New NA Information Telephone Numbers for NRC Offices Located in One White Flint North GL 92-01 Reactor Vessel Structural Integrity Closed For BLN, TVA will use the guidance of SRP Section 5.3.1 to meet the requirements of 10 CFR Part 50 Appendix H as part of the design completion activities.

GL 92-02 Resolution of Generic Issue 79, NA Information "Unanalyzed Reactor Vessel (PWR)

Thermal Stress During Natural Convection Cooldown" GL 92-03 Compilation of the Current Licensing NA Information Basis: Request for Voluntary Participation in Pilot Program GL 92-04 Resolution of Issues Related to Reactor NA BWR Vessel Water Level Instrumentation in BWRs GL 92-05 NRC Workshop on the Systematic NA Information Assessment of Licensee Performance (SALP) Program

(.i Q9-nr, Onartfnr I i ing Klational Examination NA Info.... o; Schedule GL 92-07 Office Of Nuclear Reactor Regulation NA Information Reorganization GL 92-08 Thermo-Lag 330-1 Fire Barriers Closed TVA will use the guidance of SRP Section 9.5.1.1 and R.G. 1.189 R1 in the design of any fire protection barriers as part of the design completion activities.

GL 92-09 Limited Participation by NRC in the IAEA NA Information International Nuclear Event Scale GL 93-01 Emergency Response Data System Test NA Addressed to specific plants Program Page 56 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status "FVA Action to be Completed or Justification for Closure GL 93-02 NRC Public Workshop on Commercial NA Information Grade Procurement and Dedication GL 93-03 Verification of Plant Records NA Information GL 93-04 Rod Control System Failure and Closed TVA will design the BLN rod control system using the guidance of Withdrawal of Rod Control Cluster SRP Section 4.6 as part of the design completion activities. The Assemblies, 10 CFR 50.54(f) design analysis will include an evaluation of credible control system failures.

GL 93-05 Line-Item Technical Specifications NA Information Improvements to Reduce Surveillance Requirements for Testing During Power Operation GL 93-06 Research Results on Generic Safety Issue NA Information 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" GL 93-07 Modification of the Technical Specification NA Applicable to licensed plants Administrative Control Requirements for Emergency and Security Plans GL 93-08 Relocation of Technical Specification NA Applicable to licensed plants Tables of Instrument Response Time Limits GL 94-01 Removal of Accelerated Testing and NA Applicable to licensed plants Special Reporting Requirements for Emergency Diesel Generators GL 94-02 Long Term Solutions and Upgrade of NA BWR Interim Operating Recommendations for Thermal/Hydraulic Instabilities in BWRs GL 94-03 IGSCC of Core Shrouds in BWRs NA BWR GL 94-04 Voluntary Reporting of Additional NA Information Occupational Radiation Exposure Data GL 95-01 NRC Staff Technical Position on Fire NA Does not apply to power reactors Protection for Fuel Cycle Facilities Page 57 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I &2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 95-02 Use of NUMARC/EPRI Report TR- NA Information 102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59 GL 95-03 Circumferential cracking of Steam Closed TVA will implement a Steam Generator Program, as specified in Generator (SG) Tubes NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 as part of the plant completion activities.

GL 95-04 Final Disposition of the Systematic NA Information Evaluation Program Lessons-Learned Issues GL 95-05 Voltage Based Repair Criteria for W SG NA This GL requires no specific action or written response.

Tubes Affected by Outside Diameter Stress Corrosion Cracking GL 95-06 Changes in the Operator Licensing NA Information Program GL 95-07 Pressure Locking and Thermal Binding of Closed TVA will use the guidance in SRP Section 3.9.6 for the design of Safety-Related Power-Operated Gate motor-operated valves as part of the plant completion activities.

Valves 0

GL 95-0. 10 CFR 5 .541p) Process for Changes to NA lAfoImation Security Plans Without Prior NRC Approval GL 95-09 Monitoring and Training of Shippers and NA Information Carriers of Radioactive Materials GL 95-10 Relocation of Selected Technical NA Information Specifications Requirements Related to Instrumentation GL 96-01 Testing of Safety-Related Circuits Closed TVA will evaluate the testability of the ESFAS using the guidance in SRP Section 7.3 and BTP 7-8 as part of the design completion activities.

Page 58 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units I & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 96-02 Reconsideration of Nuclear Power Plant NA Information Security Requirements Associated with an Internal Threat GL 96-03* Relocation of the Pressure Temperature Closed TVA will use NUREG-1430 B&W STS to develop Technical Limit Curves and Low Temperature Specification format for Bellefonte as part of the plant completion Overpressure Protection System Limits activities.

GL 96-04 Boraflex Degradation in Spent Fuel Pool NA Applicable to licensed plants.

Storage Racks GL 96-05* Periodic Verification of Design-Basis Closed TVA will implement a Motor-Operated Valve Testing program using Capability of Safety-Related Motor- the guidance of SRP Section 3.9.6 as part of the plant completion Operated Valves activities.

GL 96-06

• Assurance of Equipment Operability and Closed TVA will use the guidance of SRP Section 9.2.1 to design the service Containment Integrity During Design-Basis water system as part of the plant completion activities.

Accident Conditions GL 96-07 Interim Guidance on Transportation of NA Applicable to licensed plants.

Steam Generators GL 97-01* Degradation of Control Rod Drive Closed TVA will implement the in-service inspection requirements of the Mechanism Nozzle and Other Vessel ASME Code as required by 10 CFR 50.55a as part of the plant Closure Head Penetrations completion activities.

GL _97-02 Revised Contents of the Monthly NA A*pplicabl to licensed plants Operating Report GL 97-03 Annual Financial Update of Surety NA Does not apply to power reactors Requirements for Uranium Recovery Licensees GL 97-04 Assurance of Sufficient Net Positive Closed TVA will design the ECCS and containment heat removal systems Suction Head for Emergency Core Cooling using the guidance of SRP Section 6.3 and RG 1.82 R4 as part of and Containment Heat Removal Pumps the design completion activities.

GL 97-05 SG Tube Inspection Techniques Closed TVA will implement a Steam Generator Program, as specified in NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2

_as part of the plant completion activities.

Page 59 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 97-06 Degradation of SG Internals Closed TVA will implement a Steam Generator Program, as specified in NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 as part of the plant completion activities.

GL 98-01 Year 2000 Readiness of Computer NA Applicable to licensed plants Systems at Nuclear Power Plants GL 98-02 Loss of Reactor Coolant Inventory and Closed TVA will design the ECCS and containment heat removal systems Associated Potential for Loss of using the guidance of SRP Section 6.3 as part of the design Emergency Mitigation Functions While in a completion activities.

Shutdown Condition GL 98-03 NRC Generic Letter 98-03: NMSS NA Does not apply to power reactors Licensees' and Certificate Holders' Year 2000 Readiness Programs GL 98-04 Potential for Degradation of the ECCS and Closed TVA will use the guidance of SRP Section 6.1.2 to evaluate the the Containment Spray System After a containment protective coatings as part of the design completion LOCA Because of Construction and activities.

Protective Coating Deficiencies and Foreign Material in Containment GL 98-05 BWR Licensees Use of the BWRVIP-05 NA BWR Report to Request Relief from Augmented Examination Requirements on RPV Circumferential Shell Welds GL 99-01 NRC Generic Letter 99-01: Recent NA Information Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities GL 99-02 Laboratory Testing of Nuclear Grade NA Applicable to licensed plants Activated Charcoal GL 03-01 Control Room Habitability Closed TVA will use the guidance of SRP Section 6.4 for the design of the control room habitability system as part of the design completion activities, Page 60 of 61 TVA Letter dated October 10, 2012 Table 2: Generic Communications - Applicability and Status for Bellefonte Units 1 & 2 Item Title BLN Status TVA Action to be Completed or Justification for Closure GL 04-01 Requirements for SG Tube Inspection Closed TVA will implement a Steam Generator Program, as specified in NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 as part of the plant completion activities.

GL 04-02 Potential Impact of Debris Blockage on Closed See response to USI A-43.

Emergency Recirculation during Design Basis Accidents at PWRs GL 06-01 SG Tube Integrity and Associated Closed TVA will implement a Steam Generator Program, as specified in Technical Specifications NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 as part of the plant completion activities.

GL 06-02* Grid Reliability and the Impact on Plant Closed TVA will evaluate offsite power reliability using the guidance of-SRP Risk and the Operability of Offsite Power Section 8.2 as part of the design completion activities.

GL 06-03* Potentially Nonconforming Hemyc and MT Closed Hemyc and MT Fire Barrier materials addressed in this Generic Fire Barrier Configurations Letter will not be utilized for separating safe-shutdown functions within the same fire area.

GL 07-01" Inaccessible or Underground Power Cable Closed TVA will inspect/test the installed cables in accordance with the Failures that Disable Accident Mitigation Refurbishment Program described in the QVP. The guidance in RG Systems or Cause Plant Transients 1.218 will be used to develop inspection and test methods.

GL 08-01 Managing Gas Accumulation in Closed TVA will design the ECCS using the guidance of SRP Section 6.3 as Emergency Core Cooling, Decay Heat part of the design completion activities.

Removal, and Containment Spray Systems II Page 61 of 61 TVA Letter dated October 10, 2012 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units 1 & 2 1USI Status Comment Item A-i: Water Hammer Closed NUREG-0927 (March 198,4) resolves this issue. The replacement steam generator design incorporates a high-external header. TVA will conduct a preoperational vibration dynamic effects test program in accordance with Section III of the ASME code for Class 1 and 2 piping systems and piping restraints.

Item A-2: Asymmetric Closed TVA will evaluate the reactor coolant system, including the Blowdown Loads on steam generators, using the guidance in SRP Section Reactor Primary Coolant 3.9.5 as part of the design completion activities.

C-+-tmc

• G*anerator-Tube. ntegrity Item A-5: B&W Steam The original steam generators at Bellefonte will be Generator Tube Integrity replaced prior to startup. The design of the replacement steam generators reflects prior industry experience by incorporating design features and materials to address known tube damage mechanisms in operating steam generators of similar design. TVA will implement a Steam Generator Program, as specified in NUREG-1430 B&W STS using the guidance of SRP Section 5.4.2.2 as part of thp. nlqnt nnmnlpftinn nrltiviflin__

uynamric Item A-9: TVA will address the ATWS issue by meeting the requirements outlined in 10 CFR 50.62 and in the 2007 revision of NUREG 0800, SRP Chapter 7.8. Also, see rAnn~n tn ('1 R5 -9$A in Tnhhl 9 Page 1 of 4

Enclosure 1 TVA Letter dated October 10, 2012 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units I & 2 USI Status Comment Item A-1 1: Reactor Closed TVA is committed to meeting the requirements of Vessel Materials Appendix G to 10 CFR 50, including the upper shelf Toughness energy level requirements; consequently no impact of USI A-1i1 is anticipated. In addition, BLN will adopt a reactor vessel surveillance program meeting the guidelines of Appendix H to 10 CFR Part 50. For BLN, TVA will use the guidance of SRP Section 5.3.1 to meet the requirements of 10 CFR Part 50 Appendix H as part of the design completion activities.

Item A-12: Fracture Closed This issue was resolved by GL 80-46/47 - Generic Toughness of Steam Technical Activity A-12, "Fracture Toughness and Generator and Reactor Additional Guidance on Potential for Low Fracture Coolant Pump Supports Toughness and Laminar Tearing on PWR Steam Generator Coolant Pump Supports." No response was required for this GL, and NUREG-0577, "Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant Pump Supports," states that the lamellar tearing aspect of this issue was resolved by the NUREG. Further, the NUREG states that for plants under review, the fracture toughness issue was resolved.

Itemis A- 13-16 -- Dropped

,-or Resolvedl Item A-17: Systems GL 89-18 resolved this issue and required no licensee Interactions in Nuclear action.

Power Plants Iltems A-18-23 -~Dr

~or Resolved~

Item A-24: Qualification Closed The BLN EQ Program, which will meet the requirements of Class 1E Safety- of 10 CFR 50.49 using the guidance of SRP Section 3.11 Related Equipment as part of the design competition activities. As agreed by NRC in their letter dated 10/9/91, equipment procured by TVA prior to 8/31/91 will be qualified to at least the standards of NUREG 0588, Category II and IEEE 323-1971. Equipment procured after 8/31/91 will be qualified to the standards of NUREG 0588, Category I and IEEE 323-1974 unless "sound reasons to the contrary" (as defined in RG 1.89) exist. Where "sound reasons to the contrary" exist, qualification will be to at least the standards of NUREG 0588, Cateqorv II and IEEE 323-1971.

Item A ropped or Resolved Page 2 of 4 TVA Letter dated October 10, 2012 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units I & 2 USI Status Comment Item A-26: Reactor Closed TVA will meet the requirements of SRP Section 5.2 and Vessel Pressure ensure that embrittlement effects are evaluated using the Transient Protection guidance of SRP Section 5.3.1 and RG 1.99 R2 as part of the design comrletion activities..

Iltems A-27-30Q- ro~pped< 7 NA NAj

~or Resolved I Item A-31: RHR Closed In accordance with NUREG 0933, this USI was resolved Shutdown Requirements with the issuance of NURI=_G 0800, SRP Section 5.4.7.

Resolution of this issue will be accomplished by satisfying the requirements of the 2007 revision of SRP Section 5.4.7 as part of the desiqn completion activities.

Items A-32-35 - Dropped NA NA

~or Resolvedi Item A-36: Control of Closed This USI was resolved with the issuance of GL 80-113.

Heavy Loads Near Spent GL 80-113 was superseded by GL 81-07, "Control of Fuel Heavy Loads." TVA will meet the requirements of NUREG-0612, "Control of Heavy Loads at Nuclear Power Plnntc "

Item A-40: Seis Closed TVA's seismic design criteria will be based upon a design Design Criteria basis earthquake using updated GMRS site specific spectra (based on 1989 EPRI-SOG), with a minimum 0.1g earthquake, to the requirements of Appendix S, including updated soil investigation..

~N~NA<J Item A-43: Uontainment TVA will design the ECCS and containment heat removal Emergency Sump systems using the guidance of SRP Section 6.3 as part of Performance the design completion activities. TVA will install large surface area ECCS sump strainers. The strainers will be qualified by testing in accordance with the NRC approved methodologies and guidance to address GSI 191. TVA will also perform containment debris source inventory walkdowns and applicable analysis (e.g., debris generation, debris transport, chemical effects and downstream effects analysis) for BLN.

Page 3 of 4 TVA Letter dated October 10, 2012 Table 3: Unresolved Safety Issues - Applicability and Status for Bellefonte Units I & 2 USI Status Comment Item A-44: Station Closed TVA will address the Station Blackout (SBO) issue by Blackout meeting the requirements outlined in 10 CFR 50.63 and in the 2007 revision of NUREG 0800, SRP Chapter 8.4.

Specifically, TVA will perform a BLN specific analysis that includes, among other things, evaluation of EDG capacity and reliability, offsite power configuration, alternate AC power sources, SBO duration and required electrical loads.

Item A-45: Shutdown Closed SECY 88-260 stated that resolution of this issue would be Decay Heat Removal through plant specific analysis under the Individual Plant Requirements Examination (IPE) for Severe Accident Vulnerabilities..

The scope of the BLN PRA encompasses the IPE requirements. TVA will develop a plant-specific PRA using the guidance of SRP Section 19.1 as part of the design completion activities.

Item A-46: Seismic Closed The scope of Task A-46 is limited to dealing with the Qualification of seismic qualification of equipment in currently operating Equipment in Operating plants and plants holding an operating license prior to Plants 1977.

Item A-47: Safety Closed TVA will use the guidance in SRP Section 7.3 to Implications of Control incorporate automatic steam generator overfill protection Systems as part of the design completion activities.

Item A-48: Hydrogen Closed TVA will address the Hydrogen Control issue by meeting Control Measures and the requirements outlined in 10 CFR 50.44 and in the 2007 Effects of Hydrogen revision of NUREG 0800, SRP Chapter 6.2.5.

Burns on Safety Equipment Item A-49: Pressurized Closed Consistent with the conclusion statement on this USI in Thermal Shock NUREG-0933, TVA will comply with the requirements of SRP paragraph 5.3.2, including the relevant requirements of 10 CFR 50.61 and RG -1.154 to demonstrate that the reactor vessel materials are adequate for this condition.

Related actions will also be taken in response to Generic Letters 88-11 and 92-01. Specifically, TVA will perform the necessary technical analysis using the methodology provided in Regulatory Guide 1.99 revision 2 for BLN as requested in GL 88-11. In addition, BLN will adopt a reactor vessel surveillance program meeting the guidelines of Appendix H to 10 CFR Part 50. Reactor Vessel material data requested by the GL will be provided to the NRC in accordance with the GL requirements as applicable.

Page 4 of 4 TVA Letter dated October 10, 2012 List of TVA Commitments

1. TVA will take actions necessary to complete the items identified as "Open" in Tables 2 (Generic Communications) and 3 (Unresolved Safety Issues) of Enclosure 1 to this letter for BLN Unit 1.

2. TVA will provide periodic updates of the BLN Regulatory Framework tables as actions are completed.